Storage and isolation test fixture for leakage rate testing
Patent Information
- Application Number
- JP2026515116
- Authority / Receiving Office
- JP · JP
- Patent Type
- Applications
- Current Assignee / Owner
- Priority Date
- 2024-09-19
- Filing Date
- 2024-09-20
- Publication Date
- 2026-10-14
Smart Images

Figure 2026534023000001_ABST
Abstract
Description
TECHNICAL FIELD
[0001] STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH This invention was made with government support under Contract No. DE-NE0008928 awarded by the Department of Energy. The government has certain rights in the invention.
[0002] CROSS-REFERENCE TO RELATED APPLICATIONS This application claims the benefit of U.S. Provisional Patent Application No. 63 / 539,761, filed September 21, 2023, entitled "CONTAINMENT ISOLATION TEST FIXTURE (CITF) FOR LEAK RATE TESTING", and the benefit of U.S. Patent Application No. 18 / 890,676, filed September 19, 2024, entitled "CONTAINMENT ISOLATION TEST FIXTURE FOR LEAK RATE TESTING", both of which are incorporated herein by reference in their entireties. BACKGROUND ART
[0003] Nuclear reactors utilize containment isolation systems to isolate fluid systems within the reactor. Containment isolation systems provide protection for external systems from contamination and / or radiation exposure. Containment isolation systems provide means (e.g., containment isolation valves) for isolating fluid systems that pass through penetrations in the pressure vessel. Fluid systems passing through penetrations in the pressure vessel may be used to transport potentially radioactive and / or contaminated fluids.
[0004] By using a containment and isolation system, a reactor can prevent or reduce the likelihood of leakage of any radioactive fluids and / or materials downstream of the containment and isolation valve (CIV) when the CIV is closed. The CIV may be periodically tested to analyze its condition, capability, and / or reliability. The test results of the CIV may be used to verify that, in the event of an accident, the CIV can prevent or reduce the likelihood of fluids and / or materials passing through it. Typically, the CIV is tested by operating valves within the pressure vessel (i.e., the high-radioactivity area) and / or by installing temporary test fittings for use during leak testing. Temporary test fittings, not normally installed in the CIV during operation, may be installed in the CIV and then removed during testing. [Prior art documents] [Patent Documents]
[0005] [Patent Document 1] U.S. Patent Application Publication No. 2021 / 0375497 Specification [Patent Document 2] Korean Registered Patent Publication No. 10-1840677 [Patent Document 3] Chinese Patent Application Publication No. 114235307 Specification [Patent Document 4] U.S. Patent No. 11521757 [Brief explanation of the drawing]
[0006] Detailed explanations are provided with reference to the attached diagrams. In the diagrams, the leftmost digit of the reference number identifies the diagram in which the reference number first appears. The use of the same reference number in different diagrams indicates similar or identical items. Furthermore, the diagrams can be considered to provide an approximate depiction of the relative sizes of individual components within each diagram. However, the diagrams are not to scale, and the relative sizes of individual components, both within individual diagrams and across different diagrams, may differ from those depicted. In particular, some diagrams may depict components as a specific size or shape, while other diagrams may depict the same components at a larger scale or in a different shape for clarity.
[0007] [Figure 1] This paper schematically illustrates an integrated nuclear power plant system, including a power plane system, that utilizes a small reactor (SMR) system equipped with a nuclear module (NPM) that includes a containment isolation test fixture (CITF) used during containment isolation valve (CIV) leak testing. [Figure 2] This paper schematically illustrates an embodiment of an NPM integrated with a containment and isolation system (CIS) having a CITF installed upstream of a CIV. [Figure 3] This example illustrates an enlarged and lateral cross-sectional view of a portion of a CIS that utilizes the CITF upstream of the CIV. [Figure 4] An enlarged and lateral cross-sectional view of the CITF will be used as an example. [Figure 5] An example is a side cross-sectional view of another embodiment of the CITF, in which the cover is moving toward the main body of the CITF. [Figure 6A] Figures 6A to 6C illustrate exemplary top views of the positional indication of the CITF on the CITF cover. [Figure 6B] Figures 6A to 6C illustrate exemplary top views of the positional indication of the CITF on the CITF cover. [Figure 6C] Figures 6A to 6C illustrate exemplary top views of the positional indication of the CITF on the CITF cover. [Figure 7]A cross-sectional view of one embodiment of the CITF is shown, which has a spindle separated from the cover. [Figure 8] A diagram of a P&ID isolation barrier is shown to enable field leakage rate pressure testing between CNV and CIV. [Figure 9] Block diagram 900, which includes various conditions related to the process for performing test operations, is illustrated as an example. [Figure 10] A schematic and cross-sectional view of a nuclear reactor system configured according to an embodiment of this technology. [Figure 11] A partial schematic and partial cross-sectional view of a reactor system configured according to an additional embodiment of this technology. [Figure 12] A schematic diagram of a nuclear power plant system including multiple reactors according to an embodiment of this technology. [Modes for carrying out the invention]
[0008] overview This disclosure applies to small modular reactor (SMR) systems utilizing at least one nuclear module (NPM) having a containment isolation system (CIS) integrated with a containment isolation test fixture (CITF) (e.g., containment isolation test valve, isolation test valve, etc.) placed between the containment vessel (e.g., reactor pressure vessel) and a containment isolation valve (CIV). The CIV may be a single unit comprising multiple valves (e.g., a first disk and seat fluidly connected to a second disk and a seat within the same valve body). Alternatively, the CIV may be multiple separate valves fluidly connected to each other and functioning as a single valve unit (e.g., a first valve having a second valve directly downstream of the first valve). An integrated CITF (e.g., a CITF integrated with the CIS) may allow the CIV to be leak-tested more quickly than a typical leak test operation to minimize radiation exposure to workers. An integrated CITF may reduce or eliminate false negative isolation valve test results caused by test fittings used in conventional systems.
[0009] A CITF can be assembled, installed, and operated to enable efficient and reliable testing of a CIV. The CITF may be positioned downstream of the containment vessel (e.g., SMR pressure vessel) and upstream of the CIV. The CITF may include a disk, which may be operated to engage with a sheet within the CITF to isolate the pressure downstream of the disk. The CITF may be manually adjusted using tools before and after testing the CIV to ensure, if necessary, that the CIS is under test and / or normal operating conditions. A reactor system with a CITF may be used to test the reliability and capability of the CIV before operating the reactor system.
[0010] Typically, as in conventional reactor systems, one of two CIV leak test operations may be performed to verify the operation of the CIV. If a conventional reactor system includes an isolation valve within the containment vessel, the isolation valve may be used to perform an internal isolation test of the CIV. If a conventional reactor system does not include an isolation valve within the containment vessel, a test plate isolation test of the CIV may be performed.
[0011] Both typical test operations have clear drawbacks. Regardless of the specific operation used in conventional reactor systems, CIV leak tests can utilize a portion of the CIS (i.e., upstream of the CIV) that is isolated and pressurized with the CIV closed. By closing the CIV and isolating and pressurizing a portion of the CIS using the CIV, CIV leak tests can be performed to verify the operation of the CIV within test parameters.
[0012] The isolated and pressurized portion of the CIS may be used in a conventional reactor system to test the CIV. If the isolated and pressurized portion of the CIS does not lose pressure, the CIV passes the test because fluid cannot pass downstream through the CIV while it is closed. If the pressure falls below a specified threshold while the CIV is closed, the CIV fails the test because fluid can pass through the CIV despite it being closed.
[0013] A typical internal isolation test may utilize a valve (i.e., an inner valve) and a test fitting. The inner valve may be installed inside the containment vessel. The test fitting may be installed outside the containment between the containment vessel and the CIV. This typical internal isolation test may be performed by accessing the interior of the containment vessel (e.g., to operate the inner valve, etc.). However, radiation workers may spend time inside the containment vessel while accessing the interior of the containment vessel (which increases the radiation exposure of the workers). Radiation workers may spend extended periods of time within the containment vessel of conventional nuclear reactor systems to perform test-related operations.
[0014] Test-related operations performed by radiation workers for conventional nuclear reactor systems can be lengthy and time-consuming. The test-related operations may include operating the inner valve before and after the test. For example, an inner valve that is closed before the test is initiated and opened after the test is completed may allow the CIV to be tested for leakage. A portion of the CIS between the closed inner valve and the CIV may then be pressurized through the test fitting to test the CIV.
[0015] This typical internal isolation test may provide false-negative leak test results if the test fitting is leaking. Typical test operations of conventional nuclear reactor systems may not be able to be used to determine within test parameters whether a leak is from a temporary test fitting or from a failed CIV. Typical internal isolation tests may also cause excessive radiation exposure to the worker who opens and closes the inner valve, in addition to installing and removing the test fitting.
[0016] Typical test plate isolation tests can be used to test the temporary placement of blank flanges (e.g., small plates) upstream of the CIV (i.e., between the containment vessel and the CIV) in conventional reactor systems. Similar to typical internal isolation tests, typical test plate isolation tests can also produce false negative test results if the blank flange is improperly installed. Typical test plate isolation tests can also produce false negative test results if the operator is unable to identify the true cause of the leak. Identifying the true cause of the leak can be complex and time-consuming, potentially requiring operators to spend long periods in high-radiation areas. False negative leak test results can lead to unnecessary maintenance (e.g., unnecessary replacement of CIV components), resulting in excessive exposure and increased costs.
[0017] In addition to the cost of replacing unnecessary components, false negative test results can increase the downtime of conventional reactors (i.e., the time required for replacing and retesting CIV components). False negative test results that can occur in a typical test plate isolation test can increase the radiation exposure of workers replacing components in a conventional reactor during relatively long downtimes. False negative test results that can occur in a typical test plate isolation test during relatively long downtimes can result in workers spending more time in high-radiation areas. Workers may spend relatively more time in high-radiation areas, allowing them to operate the internal valve multiple times for retesting, performing unnecessary maintenance (e.g., replacing normal CIV components), etc. A typical test plate isolation test for a conventional reactor can result in the generation of a relatively large amount of radioactive waste (i.e., tools, materials, cloth, protective clothing, etc.).
[0018] In one embodiment, the CIS in a reactor system may include a containment vessel (e.g., reactor pressure vessel, reactor containment vessel, etc.), a CITF, and one or more CIVs. The CITF may include a body, a cover, and a CITF disc and disc assembly. The CITF disc and disc assembly may include a CITF disc (e.g., a ball, butterfly, etc.), a CITF front sheet (i.e., a sheet adjacent to the inlet side of the body), and a CITF back sheet (i.e., a sheet adjacent to the outlet side of the body). It should be understood that the number of sheets may vary depending on the type of valve disc used. For example, a butterfly valve disc may have only one sheet, a globe valve disc may have only one sheet, and a gate valve may have a front sheet and a back sheet, and so on. The CITF may be oriented with a specific upstream side (e.g., the side adjacent to the containment vessel) and a downstream side (e.g., the side adjacent to the CIV), and the flow passes through the CITF from the upstream side to the downstream side.
[0019] In one embodiment, the cover may be connected to the body using a dual seal to provide a leak-free joint between the cover and the body. For example, the mating surface of the cover (i.e., the surface of the cover configured to make planar contact with the cover) may include a first seal (e.g., an inner seal) and a second seal (e.g., an outer seal), separated by an area between the inner seal and the outer seal (e.g., an inner seal area). In one embodiment, the cover may include a seal test port extending from the inner seal area to the outside of the cover (i.e., creating a flow path for fluid between the inner seal area and the outside of the cover), and the seal test port may include a seal test port plug (e.g., a first port plug, a first plug, etc.) configured to connect with the cover (i.e., the seal test port plug and the seal test port plug may be threaded).
[0020] In embodiments, the CIV may include two disk and seat assemblies (or "CIV disk and seat assemblies"). A first CIV front seat (e.g., the first CIV front seat) and a first CIV disk (e.g., the first CIV disk) may be configured to be upstream of a second CIV front seat (e.g., the second CIV front seat), a second CIV disk (e.g., the second disk), and a second CIV back seat. Fluid flowing through the CIV may be directed through the first CIV front seat and the first CIV disk (e.g., the first CIV disk and seat assembly). The fluid may then pass through the second CIV front seat, the second CIV disk, and the second CIV back seat (e.g., the second CIV disk and seat assembly). Following these embodiments, the inlet to the CIV may be the upstream portion of the first CIV disk and seat assembly. The outlet to the CIV may be the downstream portion of the second CIV disk and seat assembly. It should be understood that the CIV may include a first disc and seat assembly having a front seat and a back seat, and / or the CIV may include a second disc and seat assembly having a single seat (e.g., a front seat or a back seat).
[0021] In the embodiment, the first CIV disk and seat assembly and the second CIV disk and seat assembly may be any type of disk and seat assembly found in any type of ball valve, globe valve, gate valve, or other suitable isolation valve. Individual CIV disk and seat assemblies that pass the leak test (e.g., the first CIV disk and seat assembly and the second CIV disk and seat assembly) may indicate that the CIV will pass the leak test. Confirmation of a CIV disk and seat assembly that passes the leak test (e.g., the first CIV disk and seat assembly and the second CIV disk and seat assembly) may be used as confirmation that the CIV will pass the leak test. Information indicating that any of the CIV disk and seat assemblies (e.g., the first CIV disk and seat assembly and the second CIV disk and seat assembly) will fail the leak test may be used as an indication that the CIV will fail the leak test.
[0022] In one embodiment, before performing a CIV leak test, the cover may be removed from the body of the CITF to allow access to the inside of the CITF (e.g., the CITF disk, CITF sheet, etc.). Once the cover is removed from the body, the CITF disk may be adjusted to a closed position (i.e., by rotating the disk using a tool configured to engage with an inlet inside the CITF). By adjusting the CITF disk to a closed position, the CITF disk may be adjusted so that it engages with the CITF front sheet and / or CITF back sheet (depending on which side of the CITF disk is pressurized) to close the passage between the inlet to the CITF and the outlet of the CITF. By closing the passage between the inlet to the CITF and the outlet of the CITF, the CITF prevents fluid from flowing through it. In one embodiment, the tool may be a hex wrench, a screwdriver (e.g., a flathead screwdriver, a Phillips screwdriver, a Torx screwdriver, etc.), or any other suitable device configured to extend into the body of the CITF with the cover removed to adjust the CITF disk.
[0023] In embodiments, the CITF disc may be used to allow or prevent fluid from passing through the body of the CITF. In addition to or alternative to a CITF that includes an insertion opening that can receive and be adjusted by a tool, the CITF disc may include a projection extending toward the top of the body and may require the same or a similar tool. For example, if pressure is applied downstream of the CITF disc, the CITF disc may be pushed into the CITF front sheet. However, if pressure is applied upstream of the CITF disc instead, the CITF disc may be pushed into the CITF back sheet. In exemplary embodiments, the CITF disc (e.g., a ball) may normally (e.g., during normal NPM operation) be positioned with an opening parallel to the flow through the CITF disc, allowing fluid to pass through the body without restriction (e.g., open). The CITF disc may be repositioned (e.g., rotated 90 degrees) so that the opening in the CITF disc can prevent fluid from flowing through the body of the CITF. If the CITF disk opening is positioned to block the flow through the body, the fluid can no longer pass through the body. Instead, it builds pressure against the CITF disk (e.g., closing it). The increased pressure against the CITF disk pushes the disk into one of the CITF sheets, thereby more securely sealing the CITF. Once the CIV leak test is complete, the cover may be removed again, and the CITF disk may be rotated to position the opening of the CITF disk parallel to the flow through the body.
[0024] In one embodiment, the CITF may be permanently installed in the nuclear module (i.e., the upstream side of the body (e.g., the inlet side) may be mounted outside and adjacent to the containment vessel (e.g., the reactor pressure vessel), and the downstream side of the body (e.g., the outlet side) may be mounted adjacent to the CIV). Since the NPM operates with the CITF installed, the CITF may be demonstrated to be leak-free, and therefore, if the leak test returns a negative result (e.g., no leak is detected), the CITF connection joint (e.g., the weld connecting the body to the CIS) may be ruled out as a potential source of the leak. However, in these embodiments, the CITF cover may be easily removed to provide access to the CITF disk and CITF sheet, so that a replacement CITF disk (e.g., a previously tested CITF disk verified to be leak-free) can be quickly installed for retesting. If the retest returns a negative result, the CIV may be identified as the source of the leak.
[0025] In one embodiment, performing a CIV leak test in an SMR system integrated with a CITF may include pressure testing each CIV disk and sheet assembly within the CIV. For the CIV disk and sheet assembly to pass the leak test, they may be used to maintain a threshold pressure (e.g., test pressure) over a threshold time period (e.g., test duration). By ensuring that the pressure applied as a result of the adjustment of the CIV disk and sheet assembly exceeds the threshold pressure over the threshold time period, the CIV leak test can be performed with a relatively high level of accuracy and effectiveness.
[0026] To test the first CIV disk and sheet assembly, the first CIV disk and disk assembly may be closed, a portion of the CIS between the CITF and the first CIV disk and sheet assembly (e.g., the first test portion) may be pressurized and held at a threshold pressure (e.g., test pressure) for a threshold time (e.g., test period). The results may be analyzed to verify the operation of the CITF. To test the second CIV disk and sheet assembly, the first CIV disk and sheet assembly may be opened, the second CIV disk and sheet assembly may be closed, a portion of the CIS between the CITF and the second CIV disk and sheet assembly (e.g., the second test portion) may be pressurized and held at a threshold pressure (e.g., test pressure) for a threshold time (e.g., test period), and the results may be analyzed.
[0027] A CIV leak test may be initiated by removing the CITF cover to expose the CITF disk (e.g., a ball) and CITF sheets (e.g., a CITF front sheet and a CITF back sheet). In one embodiment, the cover may include an integrated spindle portion that extends into the body and fits inside the upper portion of the disk. In an embodiment, the spindle portion may have a first end configured to engage with the CITF cover and a second end configured to engage with the CITF disk. In an embodiment, the spindle portion may be integrated with the CITF disk. The spindle portion of the CITF cover and the upper portion of the CITF disk may be configured so that the CITF disk cannot rotate within the body when the spindle portion is in the upper portion of the CITF disk (e.g., the ends of the spindle portion and the upper part of the CITF disk may have complementary keyed surfaces).
[0028] In one embodiment, the spindle portion of the cover can only be inserted into the CITF disk in a specific manner (i.e., complementary keyed surfaces can be aligned), so that when the CITF disk is rotated, the cover can also be replaced in a different orientation than when the cover was removed. For example, if the CITF disk is rotated 90 degrees clockwise, the cover may also require a 90-degree rotation clockwise to align the keyed surfaces so that the spindle can be inserted into the body.
[0029] In one embodiment, the cover may include markings on its outer surface to indicate the orientation of the CITF disk opening. For example, when the CITF disk is in the open position with the cover installed, the outer surface may have an arrow (e.g., an engraving, a raised portion, etc.) illustrated on the outside of the cover that is parallel to the fluid flow path through the body, and when the CITF disk is rotated 90 degrees to the closed position with the cover installed, the arrow illustrated on the outside of the cover may be perpendicular to the fluid flow path through the body. Alternatively or additionally, the markings on the outside of the cover may include lines or other reasonable visual locating indicators that include components necessary for remote locating.
[0030] Since the CITF is permanently installed in the SMR system during normal NPM operation, the normal operating position of the CITF may include the CITF being in the open position (i.e., the CITF is closed during CIV leak testing). It should be understood that the CITF may also be closed to isolate fluid flow through the CIS for operations other than CIV leak testing (e.g., downstream maintenance of the CITF, downstream valve replacement, various miscellaneous tests, etc.). After the CITF cover is removed, the CITF disc may be positioned in the closed position (i.e., a tool may be used to rotate the CITF disc to a position that blocks fluid flow through the body), and the CITF cover may be reinstalled.
[0031] When the cover is reinstalled, the seal test port plug may be removed, and a pressure sensing device (e.g., a pressure sensor, pressure gauge, etc.) may be installed in the seal test port. When the pressure sensing device is installed in the seal test port, the pressure sensing device may detect the pressure in the inner seal area (i.e., the area between the first seal and the second seal in the cover). In one embodiment, a pressure sensing device (e.g., a pressure sensor) may be installed in the seal test port during normal operation.
[0032] In one embodiment, when the CITF is closed and the CIS is pressurized (i.e., when the fluid is applying pressure to either the CITF front sheet or the CITF back sheet against the CITF disk), the fluid applying pressure to the CITF disk may also be felt against the inner seal of the cover. If the inner seal fails (i.e., when the fluid penetrates and / or passes through the inner seal), the fluid applying pressure to the CIS may be able to pressurize the inner seal area. A pressure sensing device connected to the inner seal area may detect the increased pressure in the inner seal area. In one embodiment, the pressure sensing device detecting the increased pressure in the inner seal area may indicate a failed inner seal that can be replaced.
[0033] After a pressure sensing device (e.g., a pressure sensor, pressure gauge, etc.) is installed in the seal test port, the first CIV disk and seat assembly in the CIV may be closed (e.g., manually, via a remote valve operator, etc.), and the leak test port plug may be removed from the leak test port. In one embodiment, a leak test port (e.g., a second port, a second test port, etc.) may be located downstream of the CITF. The leak test port may extend from the outside of the body to the downstream portion of the body (i.e., creating a fluid flow path between the first and / or second test portions and the outside of the CITF), and the leak test port may include a leak test port plug (e.g., a second port plug, a second plug, etc.) configured to connect to the body (i.e., the leak test port plug and the leak test port plug may be threaded). Once the leak test port plug is removed, a leak test device may be attached to the body via the leak test port. The test device may include a fluid pump, an isolation valve configured to block the fluid flow, and a fitting for attaching the fluid pump to the leak test port.
[0034] The leak test device can pressurize the downstream portion of the CITF (e.g., the first test portion) by pumping a fluid (e.g., an inert gas) through the leak test port. As the fluid pressurizes the downstream portion of the CITF, the fluid can push the disk in the CITF into the CITF front sheet (i.e., the CITF disk can be pushed into the CITF sheet toward the inlet side of the CITF). In an exemplary embodiment, since the CITF disk is oriented in the closed position, the fluid can push the CITF disk into the CITF front sheet of the body, and the inert gas may not be able to pass through the body of the CITF. In an exemplary embodiment, the downstream portion of the CITF is connected to an inlet to a CIV. Since a portion of the CIS downstream of the CITF is pressurized by the leak test device, the inlet portion of the CIV is also pressurized.
[0035] As the pressure downstream of the CITF increases, the pressure on the inlet side of the first CIV disc and seat assembly also increases, which pushes the first CIV disc into the first CIV backsheet and seat assembly of the first CIV disc. When a test pressure threshold (e.g., test pressure) is reached, the test pressure may be held stably for a suitable period (e.g., test period), and the results may be analyzed. Once the results have been analyzed, the first test section may be depressurized. The first CIV disc may then be opened (e.g., manually, via a remote valve operator, etc.), and the second CIV disc may be closed (e.g., manually, via a remote valve operator, etc.). In embodiments, only the CIV disc and seat assembly being tested may be closed, while the CIV disc and seat assembly not being tested may be left open (e.g., if the first CIV disc and seat assembly is closed for testing, the second CIV disc and seat assembly is open).
[0036] The leak test device can pressurize the downstream portion of the CITF (e.g., the second test portion) by pumping a fluid (e.g., an inert gas) through the leak test port. As the fluid pressurizes the downstream portion of the CITF, the fluid can push the CITF disc within the CITF into the CITF front sheet (i.e., the CITF disc can be pushed into the CITF sheet toward the inlet side of the CITF). In an exemplary embodiment, the CITF disc is oriented in a closed position, so the fluid can push the CITF disc into the CITF front sheet of the body, and the inert gas may not be able to pass through the body of the CITF. As the pressure downstream of the CITF increases, the pressure on the inlet side of the second CIV disc and sheet assembly also increases, which pushes the second CIV disc into the second CIV back sheet and sheet assembly of the second CIV disc. When a test pressure threshold (e.g., test pressure) is reached, the test pressure is held stably for an appropriate period (e.g., test period), and the results can be analyzed. Once the results have been analyzed, the second test portion can be depressurized.
[0037] In one embodiment, if the CIV test is determined to pass because no leak was detected (i.e., the test pressure was maintained throughout the test period), the CIV test process may be reversed to restore the CIS to its condition before the CIV leak test. In one embodiment, if the CIV test is determined to fail because a leak was detected (i.e., the test pressure was not maintained throughout the test period), the CITF (e.g., CITF disk, CITF front sheet, CITF back sheet, inner seal of cover) may be tested to determine if the CITF is the cause of the failure. For example, in one embodiment, a CIV test may be performed and the CIV being tested may fail because a portion of the CIS does not maintain pressure. In embodiments where the CIV test fails, the CITF may be tested to determine whether the CIV or the CITF is the cause of the leak during the test. In one embodiment, if a pressure sensing device connected to the cover of the CITF detects an increase in pressure in the inner seal area, the inner seal of the CITF may be identified as a faulty component, the inner seal may be replaced, and a new CIV leak test may be initiated. In embodiments where the CITF, or any component thereof, is determined to be the cause of the leak, the CITF can be repaired more easily than the CIV.
[0038] In one embodiment, if a pressure sensing device connected to the cover does not detect an increase in pressure, the CITF disk may be replaced with a new disk (e.g., a disk that has been pre-tested and verified not to leak). In one embodiment, if the CITF disk is replaced with a new disk and the pressure sensing device does not detect an increased pressure in the inner seal area, the particular CIV disk and sheet assembly being tested (e.g., a first CIV disk and sheet assembly, or a second CIV disk and sheet assembly) may be determined to be the source of the leak.
[0039] Exemplary Embodiment of a Containment and Isolation Test Fixture Figure 1 schematically illustrates an integrated nuclear power plant system 100, which includes a power plant system 102 that uses a small reactor (SMR) system 104 equipped with a nuclear module (NPM) 106 having a containment isolation test fixture (CITF) 108 used during containment isolation valve (CIV) leak testing.
[0040] In the illustrated embodiments, the SMR system 104 may include a multimodule power plant design having a similar NPM. However, in various cases, the SMR system 104 may represent any type of power plant system that includes any of various other types of reactors and / or reactor systems. For example, the power plant system 102 may include multiple small modular reactors of the same or different sizes or operating characteristics.
[0041] Within the SMR system 104, the CITF 108 may be integrated into the containment isolation system (CIS) of the NPM 106. The CIS of the NPM 106 may be configured to prevent and / or limit the release of radioactive material outside the containment vessel (e.g., reactor pressure vessel) as needed (i.e., in the event of a nuclear accident, environmental accident, maintenance, etc.). Because the CIS may depend on the emergency situation, the CIS may be periodically tested to ensure that the CIV does not allow fluid to flow through the CIS when the CIS is configured to block fluid flow through the CIS (e.g., when the containment vessel is set up, when the CIS is fixed, etc.). In one embodiment, the CIS of the NPM 106 may include the CITF 108 and the CIV. It should be understood that the CIV may include multiple isolation valves in one housing (i.e., a first disk and seat assembly 330 and a second disk and seat assembly 332 in one housing) and / or multiple individual adjacent valves that function as a single CIV. In one embodiment, NPM106 may include a containment vessel that may have one or more CIVs within the CIS.
[0042] In one embodiment, CITF108 may be used to isolate a portion of CIS for CIV leak testing. In an exemplary embodiment, CITF108 and CIV may be closed, and a portion of CITF108 and CIV (e.g., a first disc and seat assembly in the housing or a first isolation valve) may be pressurized to determine whether fluid can flow through the CIV. In an exemplary embodiment, CITF108 may remain closed while an additional valve is being leak-tested (e.g., an additional CIV, an isolation valve, or any other valve fluid-connected downstream of CITF108).
[0043] Figure 2 schematically illustrates an embodiment of the NPM200 integrated with a containment and isolation system (CIS) 204 having a CITF 206 installed upstream of the CIV 208. The CITF 206 can be used to perform CIV leak testing more quickly, more reliably, and with less radiation exposure for the operator. The CIS 204 may include a containment vessel 202, a CITF 206, and a CIV 208. It should be understood that the CIV may include a single valve body housing multiple valves (i.e., a first disc and seat assembly 330 and a second disc and seat assembly 332 within the CIV 208). It should also be understood that the CIS 204 may include multiple containment vessels, CITFs, and / or CIVs.
[0044] NPM200 may be the same as or similar to NPM106, as discussed above with reference to Figure 1. In one embodiment, the CIS may be used to prevent the release of radioactive material outside the containment vessel (e.g., reactor pressure vessel) as needed (i.e., in a nuclear accident, environmental accident, maintenance, etc.) (e.g., to reduce the release of radioactive material outside the containment vessel to below a predetermined and / or threshold level). To ensure the reliability of the CIV's ability to reduce the release of radioactive material to below a predetermined and / or threshold level, the CIV may be leak-tested to verify that when the CIV is closed, the CIV does not allow fluid to leak through the CIV within test tolerances and / or protocols. In embodiments in which the CIV includes multiple disk and seat assemblies within a single housing (as shown in Figure 2), each disk and seat assembly may be leak-tested separately. Similarly, in embodiments in which the CIV includes multiple individual valves fluidically connected in series (i.e., directly adjacent to one another), each individual valve may be leak-tested.
[0045] In one embodiment, the CIV may be leak-tested by isolating a first portion of the CIS (e.g., a first test portion) to allow the pressure to be directed toward the first disk and sheet assembly. For example, the first test portion may include the CITF 206 and the first disk and sheet assembly 330. Once the first test portion is isolated, it may be pressurized with a test fluid (i.e., an inert gas, etc.) until the first test portion reaches a specific pressure (e.g., a first test pressure). After the first test portion is at the first test pressure, it may be observed for a specific duration (e.g., a first test period) to ensure that the first disk and sheet assembly can prevent leakage during sustained pressurization. In one embodiment, the first test portion may then be depressurized, and the CIS may be configured to isolate a second portion of the CIS (e.g., a second test portion) to allow the pressure to be directed toward the second disk and sheet assembly. For example, the second test section may include the CITF206 and the second disc and sheet assembly 332. The second test section may be pressurized, observed, and the results analyzed.
[0046] In one embodiment, a CIV leak test may be completed when one or more disk and sheet assemblies within the CIV (e.g., all disk and sheet assemblies) are leak-tested. If all disk and sheet assemblies within the CIV are leak-tested and no leaks are found, the CIV may be classified as having passed the CIV leak test. If any of the disk and sheet assemblies within the CIV is found to allow flow through the disk and sheet assembly despite being closed, the CIV may be classified as having failed the CIV leak test.
[0047] Figure 3 illustrates an enlarged and lateral cross-sectional view of a portion of the CIS300 ("CIS300") that utilizes the CITF206 (e.g., isolation test valve) upstream of the CIV208. In one embodiment, the CIS300 may, for illustrative purposes only, include a portion of the containment vessel 302 shown by shaded areas as in Figure 3, which is integral to and not separate from any remaining portion of the containment vessel 302. In some examples, a portion of the containment vessel 302 may be used to implement a corresponding portion of the containment vessel 202, as discussed above with reference to Figure 2.
[0048] A portion of the containment vessel (also referred to herein simply as the “containment vessel”) 302 (e.g., the reactor pressure vessel) may be included within the CIS300 together with the CITF206 and CIV208. The CITF206 may include a body 304, a cover 306, and a disc and disc assembly 308. The disc and disc assembly 308 may include a disc 310 (e.g., a ball, butterfly, etc.), a front sheet 312 (i.e., a sheet adjacent to the inlet side of the body), and a back sheet 314 (i.e., a sheet adjacent to the outlet side of the body). The disc 310 may be configured to receive an operating tool (e.g., a hex wrench, Phillips screwdriver, flathead screwdriver, Torx screwdriver, key, etc.) and rotate in an open or closed position. For example, when the cover 306 is removed, an operating tool may be inserted into the body and engage with the disc 310, rotating the disc 310 to a desired position.
[0049] Although illustrated in Figure 3 as having a front seat and a back seat, please understand that the CITF206 may contain only a single seat. Also, please understand that only a single seat may be required for CIV testing. Please understand that the number of seats may vary depending on the type of valve disc used and / or the desired application. For example, a butterfly valve disc may have only one seat, a globe valve disc may have only one seat, and a gate valve may have both a front seat and a back seat. The CITF206 may be oriented with a specific upstream side (e.g., the side closer to the containment vessel) and a downstream side (e.g., the side closer to the CIV208), and the flow passes through the CITF206 from the upstream side to the downstream side.
[0050] In one embodiment, the cover 306 may be connected to the body 304 using a dual seal 316 to provide a leak-free joint between the cover 306 and the body 304. For example, the mating surface of the cover 306 (i.e., the surface of the cover 306 configured to make planar contact with the body 304) may include a first seal 318 (e.g., an inner seal) and a second seal 320 (e.g., an outer seal), separated by an area between the inner seal 318 and the outer seal 320 (e.g., an inner seal area). The first seal 318 may include a first side adjacent to the center of the body 304 and a second side opposite to the first side, adjacent to the second seal 320. The second seal 320 may include a first side adjacent to the first seal 318 and a second side opposite to the first side, which is not as close to the center of the body 304 as the first side of the second seal 320.
[0051] In one embodiment, the cover 306 may include a seal test port 322 ("port 322") (e.g., first test port, first port, etc.) having a first side and a second side opposite the first side, the first side being closer to the center of the body 304 than the second side. The port 322 may extend from the inner seal area to the outside of the cover 306 (i.e., creating a flow path for fluid between the inner seal area and the outside of the cover 306), and the test port 322 may include a seal test port plug 324 ("plug 324") (e.g., first port plug, first plug, etc.) configured to connect with the cover 306 (i.e., the plug 324 and port 322 may be threaded). The seal test port 322 may be disposed through the cover 306 such that the seal test port 322 extends between the first side of the first seal 318 and the first side of the second seal 320. For example, the first side of port 322 may be located adjacent to the first side of the first seal 318, and the second side of port 322 may be located adjacent to the first side of the second seal 320.
[0052] In one embodiment, the body 304 may include a port 326 (e.g., a second test port, a second port, etc.) and a plug 328. In this embodiment, the port 326 (e.g., a second port, a second test port, etc.) may be located downstream of the disk 310. The port 326 may extend from the outside of the body 304 to the downstream portion of the body 304 (i.e., creating a flow path for fluid between the first and / or second test portions and the outside of the body 304). The plug 328 (e.g., a second port plug, a second plug, etc.) may be configured to connect to the body 304 and seal the port 326 (i.e., the plug 328 and the port 326 may be threaded). When the plug 328 is removed, a leak test device (not shown) may be attached to the body 304 via the port 326. The test device may include a fluid pump, an isolation valve configured to prevent backflow through the pump, and a fitting for attaching the fluid pump to the port 326. It should be understood that port 322 may be on the first side (e.g., the upstream side) of the disk and seat assembly 308, and port 326 may be on the second side (e.g., the downstream side) of the disk and seat assembly 308.
[0053] In the embodiment, CIV208 may include a disc and seat assembly 330 (e.g., a first disc assembly, or "first valve"). CIV208 may also include a disc and seat assembly 332 (e.g., a second disc and seat assembly, or "second valve").
[0054] The disc and seat assembly 330 may include a front seat 334 (e.g., a first front seat) and a disc 336 (e.g., a first disc). In embodiments, the CIV 208 may include a cover 338. The cover 338 may be configured to connect with the CIV 208. In embodiments, the cover 338 may be removed to provide access to the internal components of the disc and seat assembly 330 (e.g., the front seat 334, the disc 336, etc.). In embodiments, the cover 338 may include one or more marks or other identifying markings on the top surface of the cover 338 that can function as a visual indicator of the state of the disc and seat assembly 330 (e.g., flow direction, open position, closed position, etc.). For example, the cover 338 may include an arrow indicating the direction in which the fluid will flow through the disc and seat assembly 330.
[0055] In one embodiment, the disc and seat assembly 330 may include a single seat ball valve to enable thermal overpressure protection. In the assembly, the disc and seat assembly 330 may include an upstream seat to satisfy the requirements of ANSI / ANS56.2. The disc and seat assembly 332 may include a front seat 340 (e.g., a second front seat), a disc 342 (e.g., a second disc), and a back seat 344. In one embodiment, the disc and seat assembly 332 may include a dual-seal ball valve for bidirectional adaptability. The fluid flow through the CIV208 may be directed through the front seat 340, disc 342, and back seat 344 (e.g., the disc and seat assembly 332), as well as the front seat 334 and disc 336 (e.g., the disc and seat assembly 330) before passing through the front seat 340, disc 342, and back seat 344 (e.g., the disc and seat assembly 332), and the downstream pipe end of the CIV208.
[0056] In these embodiments, the inlet to the CIV208 may be the upstream portion of the disc and seat assembly 330, and the outlet to the CIV208 may be the downstream portion of the disc and seat assembly 332. In embodiments, the disc and seat assembly 330 and the disc and seat assembly 332 may be similar to typical disc and seat assemblies found in typical ball valves, globe valves, gate valves, or other suitable isolation valves. In some cases, the CIV208 may pass the CIV leak test if both the CIV disc and seat assemblies (330 and 332) each pass their respective individual leak tests. In some cases, the CIV208 may pass the CIV leak test if both CIV front seats (334 and 340) each pass their respective individual leak tests. For example, verifying CIV208 as passing the CIV leak test may be based on the fact that all CIV disks and sheet assemblies (e.g., both CIV disks and sheet assemblies (330 and 332)) have passed the CIV leak test. In such an example, or in another example, a CIV208 that fails the CIV leak test may be determined on the fact that any CIV disk and sheet assembly (e.g., either or both of CIV disks and sheet assemblies (330 and 332)) has failed the CIV leak test.
[0057] Before performing a CIV leak test, the cover 306 may be removed from the body 304 of the CITF 206 to allow access to the inside of the CITF (e.g., the disk 310, front sheet 312, back sheet 314, etc.). Once the cover 306 is removed from the body 304, the disk 310 may be adjusted to position the disk 310 so that it engages with the front sheet 312 and / or back sheet 314 (depending on which side of the disk 310 is pressurized) and can restrict the flow through the CITF 206 (i.e., using a tool configured to engage with and rotate the disk). In one embodiment, the tool may be a hex wrench, a screwdriver (e.g., a flathead screwdriver, a Phillips screwdriver, a Torx screwdriver, etc.), or any other suitable device configured to extend into the body 304 of the CITF 206 with the cover 306 removed to adjust the disk 310. Additionally, or alternatively, the disk 310 may include a projection extending toward the top of the body 304, and the same or similar tools may be required to position the disk 310.
[0058] In one embodiment, the plug 328 may be detached from the body 304, and the leak test device may be attached to the body 304, and the leak test device may pump a test fluid (e.g., an inert gas) into the body 304 via the port 326 to increase the pressure in the isolated portion of the CIV. For example, if pressure is applied downstream of the disk 310, the disk 310 may be pushed into the front sheet 312, but conversely, if pressure is applied upstream of the disk 310, the disk 310 may be pushed into the back sheet 314. In an exemplary embodiment, the disk 310 (e.g., a ball) may normally (e.g., during normal NPM operation) be positioned with an opening parallel to the flow through the disk 310, allowing the fluid to pass through the body 304 without restriction (e.g., open). The disk 310 may be repositioned (e.g., rotated 90 degrees) so that the opening in the disk 310 can restrict the fluid flow through the body 304. When the opening in the disk 310 is positioned to control (e.g., restrict, block, limit) the flow through the body 304, the fluid can be controlled so that it no longer passes through the body 304. Instead, the fluid can build up pressure against the disk 310 (e.g., close). The increased pressure against the disk 310 can push the disk 310 into one of the CITF sheets (e.g., the front sheet 312 or the back sheet 314), thereby more reliably sealing the CITF 206. Once the CIV leak test is complete, the cover 306 may be removed again, and the disk 310 may be rotated to position the opening of the disk 310 so that the opening is parallel to the flow through the body.
[0059] As discussed above in this disclosure, CIS300 includes, but is not limited to, a single valve (e.g., CITF206) for testing assemblies 330 and / or 332. In some examples, CIS300 includes two or more fixtures (e.g., two or more valves) that are similar to or different from CITF206, and / or operate similarly to or differently from CITF206. For example, any of the two or more fixtures may include a fixture with a single seat, a fixture with two seats, any other type of fixture, or any combination thereof.
[0060] Figure 4 illustrates an enlarged and lateral cross-sectional view of the CITF206 in Figures 2 and 3. The enlarged and cross-sectional view of the CITF206 shows a more detailed enlarged view of the orientation and operation of the CITF206, cover 306, disc and seat assembly 308, disc 310, front seat 312, back seat 314, dual seal 316, first seal 318, second seal 320, port 322, plug 324, port 246, and plug 328.
[0061] In one embodiment, as shown in Figure 4, the cover 306 may include a spindle portion 400 integrated with the cover 306. For example, the spindle portion 400 may include a spindle. The spindle portion 400 may extend into the body 304 and fit inside the upper portion of the disk 310. The spindle portion 400 of the cover 306 and the upper portion of the disk 310 may be configured such that the disk 310 cannot rotate within the body 304 when the spindle portion is in the upper portion of the disk 310 (for example, the ends of the spindle portion 400 and the upper part of the disk 310 may have complementary keyed surfaces). It should be understood that in some embodiments, the spindle portion may be separated from the cover 306. It should also be understood that in some embodiments, the spindle portion may be integrated with the disk 310 (i.e., the disk 310 may include a spindle portion extending upward toward the cover 306).
[0062] In one embodiment, the spindle portion 400 of the cover 306 can only be inserted onto the disk 310 in a specific manner (i.e., complementary keyed surfaces can be aligned), so when the disk 310 is rotated, the cover 306 can also be replaced in a different orientation than when the cover was removed (for example, the cover 306 can also be rotated). For example, if the disk 310 is rotated 90 degrees clockwise, the cover 306 may also require a 90-degree clockwise rotation to align the keyed surface of the spindle portion 400 with the upper portion of the disk 310, so that the spindle portion 400 can be fully inserted onto the disk 310, and thus the cover 306 can be fully sealed against the body 304.
[0063] Figure 5 illustrates a side cross-sectional view of another embodiment of the CITF500. For example, the CITF500 may include a test port with local position indicators (e.g., test port 520) and a cover (e.g., first cover 504).
[0064] In one embodiment, the CITF500 may include a body 502, a first cover 504, a second cover 506, a disk 508, and a sheet 510. The first cover 504 may include a seal 512 and a dual key 514. The second cover 506 may include a seal 516 and a dual key 518. The body 502 may include a test port 520. In various examples, the CITF500 may be used to implement the CITF206 as discussed above with reference to Figures 2 and 3. While the CITF206 is illustrated from one viewpoint (e.g., a side view), the CITF500 is illustrated from another viewpoint (e.g., another side view).
[0065] In various examples, the first cover 504 may be moved toward the body 502. The first cover 504 may be positioned toward the body 502 to form a seal between the first cover 504 and the body 502. The seal between the first cover 504 and the body 502 may be firm and liquid-tight. The first cover 504 may be moved toward one side of the body 502 (e.g., the top side) and positioned opposite to it.
[0066] In those or other examples, the second cover 506 may be moved toward the body 502. The second cover 506 may be positioned opposite the body 502 to form a seal between the second cover 506 and the body 502. The seal between the second cover 506 and the body 502 may be firm and liquid-tight. The second cover 506 may be moved toward one side of the body 502 (e.g., the bottom) and positioned opposite it.
[0067] In various examples, securing the first cover 504 to the body 502 includes threaded fasteners, studs and nuts, or any other reasonable and faster method. In these or other examples, the second cover 406 may be secured to the body 502 in a similar or different manner to the first cover 504 that is secured to the body 502.
[0068] Figures 6A–6C illustrate exemplary top views of a CITF cover 600 for a CITF 206, integrated with a visual indication of the location of the CITF 206 and / or the flow direction through the CITF 206. For example, the CITF 206 may include a cover (e.g., a first cover 504 and / or a second cover 506, as discussed above with reference to Figure 5) and a test port (e.g., a test port 520, as discussed above with reference to Figure 5). Individuals of the first cover 504 and / or the second cover 506 may have an indicator of whether the port is open or closed. The test port may be located adjacent to a containment isolation valve.
[0069] In embodiments, the CITF cover 600 may include one or more openings 602. In embodiments, the CITF cover 600 may include a flow indicator 604. It should be understood that the flow indicator 604 may include a visual representation of direction (e.g., an arrow) and / or a linguistic representation (e.g., flow).
[0070] In some embodiments, the opening 602 may be sized and configured to receive fasteners used to connect the CITF cover 600 to the CITF 206. In some embodiments, the opening may be sized to receive one or more projections extending from the CITF body (not shown), which may be useful during the installation and / or removal of the CITF cover 600 (e.g., ensuring alignment between the CITF cover and the CITF under low visibility conditions, providing support to the CITF cover 600 when fasteners are installed and / or removed). Although the openings 602 are illustrated as uniformly sized in Figures 6A–6C, in embodiments, the size of each opening 602 may be sized according to its purpose. For example, an opening configured to receive fasteners may be appropriately sized for fasteners, while an opening configured to receive alignment pins may be appropriately sized and shaped for alignment pins.
[0071] It should be understood that the CITF cover 600 may include any suitable number of openings 602 as desired (i.e., a CITF cover 600 with a larger diameter may include more openings than a CITF cover 600 with a smaller diameter). It should also be understood that the size of each opening 602(a-n) may vary.
[0072] Figure 6A illustrates a top view of one embodiment of a CITF cover 600 utilizing a flow indicator 604. While Figure 6A illustrates the linguistic expression as "flow" in English, it should be understood that the linguistic expression can be any word in any language as needed. In one embodiment, the CITF cover 600 may be positioned such that the flow indicator 604 is parallel to the fluid flow path through the disk 310 of the CITF 206 in order to provide a visual indication of the current orientation of the disk 310. For example, before the CITF cover 600 is removed, the flow indicator 604 may indicate a flow oriented parallel to the flow path through the CITF 206. The CITF cover 600 may be removed, and the disk 310 may be rotated 90 degrees. The CITF cover 600 may be rotated 90 degrees and reinstalled on the CITF 206. The flow indicator 604 provides an immediate visual indication of the position of the disk 310 without requiring the removal of the CITF cover 600.
[0073] Figure 6B illustrates a top view of one embodiment of a CITF cover 600 utilizing a position indicator 606. In one embodiment, the position indicator 606 may include external components (i.e., a portion of the valve position indicator is outside the CITF cover 600). For example, in one embodiment, the cover may include a visible arrow, which is positioned at various locations adjacent to the CITF cover 600. In the example, the CITF cover 600 may be oriented such that the arrow on the CITF cover 600 points to a valve location adjacent to the CITF cover 600. In one embodiment, the CITF cover 600 may be positioned such that a flow indicator 604 may be parallel to the fluid flow path through the disk 310 of the CITF 206 in order to provide a visual indication of the current orientation of the disk 310. For example, before the CITF cover 600 is removed, the flow indicator 604 may show a flow oriented parallel to the flow path through the CITF 206. The CITF cover 600 may be removed, and the disk 310 may be rotated 90 degrees. The CITF cover 600 can be rotated 90 degrees and reinstalled on the CITF 206. The flow indicator 604 provides an immediate visual indication of the disk 310's position without requiring the removal of the CITF cover 600.
[0074] Figure 6C illustrates a top view of one embodiment of a CITF cover 600 utilizing a flow indicator 604 and a position indicator 608. In one embodiment, the CITF cover 600 may be positioned such that the flow indicator 604 may be parallel to the fluid flow path through the disk 310 of the CITF 206 in order to provide a visual indication of the current orientation of the disk 310. In one embodiment, the position indicator 608 may include a linguistic indication of the orientation of the disk 310 of the CITF 206. In an embodiment, the position indicator may include several words in which only one of the words is properly oriented for reading. For example, when the CITF cover 600 is oriented to allow flow through the CITF 206, the OPEN indicator may be oriented correctly up and down, while other words may be upside down and / or sideways.
[0075] Figure 7 shows a cross-sectional view of the containment isolation test fixture 700. 708 indicates the upper side of the containment isolation valve, and 710 indicates the bottom side of the containment vessel. The cover 704 is bolted or locked and keyed at the ball position and includes a local position indicator on the top of the cover. The cover 704 includes a double cover 702 having a test port and a plug. The stem 706 is centrally located and does not protrude beyond the cover 704. The test plug 712 is disposed on the opposite side of the cover 704. A one-way seal 714 is provided between the containment isolation valve and the containment vessel.
[0076] Figure 8 shows a piping and instrumentation diagram ("P&ID") illustrating the need for an isolation barrier to enable field leakage rate pressure testing between the containment vessel ("CNV") and the CIV. The boundary and two containment isolation valves are located outside the containment vessel. The test port is located between the boundary and the two containment isolation valves.
[0077] Figure 9 illustrates block diagram 900, which has various conditions related to the process for performing a test operation. The order in which the process operations or steps are described is not intended to be constrained, and any number of described operations and / or conditions can be combined in any order and / or in parallel to operate CITF206 (e.g., CITF206 as discussed above with reference to Figures 2, 3, and 4) and perform a test operation.
[0078] Various pre-test conditions 902 may be used to carry out and / or as part of a process for carrying out a test operation. Pre-test conditions 902 may include removing the cover 306 and rotating the disk 310 so that the disk 310 is oriented to block the fluid flow through the body 304. Pre-test conditions may include rotating the cover 306 so that the flow indicator 604 and / or position indicators (606 / 608) are oriented to indicate that the test valve is closed. Pre-test conditions may include reinstalling the cover 306 on the body 304. Pre-test conditions may include ensuring that the CIV 208 (e.g., the CIV being tested) is closed, that a pressure monitoring system is attached to port 322, and that a leak test system is attached to port 326.
[0079] The process may include various test operations 904. For example, the process may include injecting fluid through a leak test system via port 326, pressurizing the isolated portion of CITF206 with the fluid, and pressurizing the isolated portion of CITF206 using the pressurized fluid. The process may include maintaining the test pressure over a specified test period and, upon reaching the specified test period, depressurizing the isolated portion of CITF206.
[0080] Various post-test conditions 906 may be used on the basis of and / or implemented as part of the process for performing the test operation. Post-test conditions 906 may include the removal of a pressure monitoring system (e.g., attached to port 322). Post-test conditions 906 may include the removal of a leak test system (e.g., attached to port 326). Post-test conditions 906 may include the opening of CIV 208 (e.g., the CIV being tested). Post-test conditions 906 may include the removal of cover 306. Post-test conditions 906 may include the rotation of disc 310 so that it is oriented to allow fluid flow through body 304. Post-test conditions 906 may include the rotation of cover 306 so that flow indicator 604 and / or position indicators (606 / 608) are oriented to indicate that the test valve is open. Post-test conditions 906 may include the reinstallation of cover 306.
[0081] Figures 10 and 11 illustrate typical reactors that may be included in embodiments of the present technology. Figure 10 shows a schematic diagram of an exemplary reactor module for connection with a pressure swing adsorption system. In one embodiment, the reactor module may be a pressurized water reactor (PWR), but may be different types of reactors utilizing various fuels and located on land, at sea, and in extraterrestrial locations. Figure 10 shows a typical reactor that may be included in embodiments of the present technology. Figure 10 is a partial schematic, partial cross-sectional view of a reactor system 1000 configured according to an embodiment of the present technology. The system 1000 may include a power module 1002 having a core 1004 in which a controlled nuclear reaction takes place. Thus, the core 1004 may include one or more fuel assemblies 1001. The fuel assemblies 1001 may include fissile and / or other suitable materials. The heat from the reaction generates steam in a steam generator 1030, where the steam is directed to a power conversion system 1040. The power conversion system 1040 generates electricity and / or other useful outputs such as superheated steam. The sensor system 1050 is used to monitor the operation of the power module 1002 and / or other system components. The data acquired from the sensor system 1050 can be used to control the power module 1002 in real time and / or to update the design of the power module 1002 and / or other system components.
[0082] The power module 1002 then includes a containment vessel 1010 (e.g., a radiation shielding vessel or radiation shielding container) that houses / encloses a reactor vessel 1020 (e.g., a reactor pressure vessel or reactor pressure container) that houses the reactor core 1004. The containment vessel 1010 can be housed in a power module bay 1056. The power module bay 1056 may include a cooling pool 1003 filled with water and / or another suitable cooling fluid. The majority of the power module 1002 can be located below the surface 1005 of the cooling pool 1003. Thus, the cooling pool 1003 can act as a heat sink, for example, in the event of a system malfunction.
[0083] The volume between the reactor vessel 1020 and the containment vessel 1010 can be partially or completely evacuated to reduce heat transfer from the reactor vessel 1020 to the surrounding environment (e.g., the cooling pool 1003). However, in other embodiments, the volume between the reactor vessel 1020 and the containment vessel 1010 can be at least partially filled with gases and / or liquids that increase heat transfer between the reactor vessel 1020 and the containment vessel 1010. For example, the volume between the reactor vessel 1020 and the containment vessel 1010 can be at least partially filled (e.g., filled with primary coolant 1007) during emergency operations.
[0084] Within the reactor vessel 1020, the primary coolant 1007 carries heat from the core 1004 to the steam generator 1030. For example, as illustrated by the arrows located within the reactor vessel 1020, the primary coolant 1007 is heated in the core 1004 toward the bottom of the reactor vessel 1020. The heated primary coolant 1007 (e.g., water with or without additives) rises from the core 1004 through the core shroud 1006 to the riser tube 1008. The hot, buoyant primary coolant 1007 continues to rise through the riser tube 1008 and then exits the riser tube 1008 and passes downward through the steam generator 1030. The steam generator 1030 includes a number of conduits 1032 arranged circumferentially around the riser tube 1008, for example in a helical pattern, as schematically shown in Figure 10. The descending primary coolant 1007 transfers heat to the secondary coolant (e.g., water) in the conduit 1032 and descends to the bottom of the reactor vessel 1020, where the cycle is restarted. The cycle can be driven by the change in buoyancy of the primary coolant 1007, thus reducing or eliminating the need for pumps to move the primary coolant 1007.
[0085] The steam generator 1030 may include a feedwater header 1031 into which incoming secondary coolant enters the steam generator conduit 1032. The secondary coolant rises through the conduit 1032, is converted into vapor (e.g., steam), and collected in the steam header 1033. The steam exits the steam header 1033 and is directed to the power conversion system 1040.
[0086] The power conversion system 1040 may include one or more steam valves 1042 that regulate the passage of high-pressure, high-temperature steam from the steam generator 1030 to the steam turbine 1043. The steam turbine 1043 converts the thermal energy of the steam into electricity via a generator 1044. The low-pressure steam exiting the turbine 1043 is condensed in a condenser 1045 and then directed to one or more feedwater valves 241 (e.g., via a pump 1046). The feedwater valves 1041 control the rate at which the feedwater re-enters the steam generator 1030 via a feedwater header 1031. In other embodiments, the steam from the steam generator 1030 can be routed for direct use in industrial processes such as hydrogen (H2) and oxygen (O2) production plants, chemical production plants, and / or similar, as described in detail below. Thus, the steam exiting the steam generator 1030 can bypass the power conversion system 1040.
[0087] The power module 1002 includes a number of control systems and associated sensors. For example, the power module 1002 may include a hollow cylindrical reflector 1009 that returns neutrons into the core 1004 to further accelerate the nuclear reaction occurring therein. Control rods 1013 are used to regulate the nuclear reaction and are driven via a fuel rod driver 1015. The pressure inside the reactor vessel 1020 can be controlled via the pressurizer plate 1017 by controlling the pressure in a pressurized volume 1019 located above the pressurizer plate 1017 (this can also function to direct the primary coolant 1007 downward through the steam generator 1030).
[0088] The sensor system 1050 may include, for example, one or more sensors 1051 located in various places within and / or elsewhere in the power module 1002 to identify operating parameter values and / or changes in parameter values. The data collected by the sensor system 1050 can then be used to control the operation of system 1000 and / or to cause design changes for system 1000. For sensors located within the containment vessel 1010, the sensor link 1052 directs data from the sensor to flange 1053 (where the sensor link 1052 exits the containment vessel 1010) and to the sensor junction box 1054. From there, the sensor data can be routed via data bus 1055 to one or more controllers and / or other data systems. The containment vessel 1010 and containment system in Figure 10 should ensure that the containment vessel's leak integrity is maintained.
[0089] Figure 11 is a partial schematic, partial cross-sectional view of a reactor system 1100 configured according to additional embodiments of the present technology. In some embodiments, the reactor system 1100 ("System 1100") may include several features that are at least generally similar in structure and function to, or identical in structure and function to, the corresponding features of System 1100 described above in detail with reference to Figure 11, and may operate in a manner generally similar to or identical to System 1100.
[0090] In the illustrated embodiments, the system 1100 includes a furnace vessel 1120 and a containment vessel 1110 surrounding / enclosing the furnace vessel 1120. In some embodiments, the furnace vessel 1120 and the containment vessel 1110 may be approximately cylindrical or capsule-shaped. The system 1100 further includes a plurality of heat pipe layers 1111 within the furnace vessel 1120. In the illustrated embodiments, the heat pipe layers 1111 are spaced apart from each other and stacked. In some embodiments, the heat pipe layers 1111 can be mounted / secured to a common frame 1112, a portion of the furnace vessel 1120 (e.g., its walls), and / or other suitable structures within the furnace vessel 1120. In other embodiments, the heat pipe layers 1111 can be stacked directly on top of each other such that each heat pipe layer 1111 supports and / or is supported by one or more of the other layers of heat pipe layers 1111.
[0091] In the illustrated embodiments, the system 1100 further includes a shielding or reflector region 1114 that at least partially surrounds the core region 1116. The heat pipe layer 1111 can be circular, linear, polygonal, and / or have other shapes, so that the core region 1116 has a corresponding three-dimensional shape (e.g., cylindrical, spherical). In some embodiments, the core region 1116 is separated from the reflector region 1114 by a core partition 1115, such as a metal wall. The core region 1116 may include one or more fuel sources, such as fissile material, for heating the heat pipe layer 1111. The reflector region 1114 may include one or more materials configured to contain / reflect products generated by burning fuel within the core region 1116 during the operation of the system 1100. For example, the reflector region 1114 may include a liquid or solid material configured to reflect neutrons and / or other fission products radially inward toward the core region 1116. In some embodiments, the reflector region 1114 may completely surround the core region 1116. In other embodiments, the reflector region 1114 may partially surround the core region 1116. In some embodiments, the core region 1116 may include control material 1117 such as a moderator and / or coolant. The control material 1117 may at least partially surround the heat pipe layer 1111 within the core region 1116, allowing heat to be transferred between them.
[0092] In the illustrated embodiments, the system 1100 further includes at least one heat exchanger 1130 (e.g., a steam generator) arranged around the heat pipe layer 1111. The heat pipe layer 1111 may extend at least partially from the core region 1116 into the reflector region 1114 and be thermally coupled to the heat exchanger 1130. In some embodiments, the heat exchanger 1130 may be located outside the reflector region 1114 or partially within the reflector region 1114. The heat pipe layer 1111 provides a heat transfer path from the core region 1116 to the heat exchanger 1130. For example, each heat pipe layer 1111 may include an array of heat pipes that provide a heat transfer path from the core region 1116 to the heat exchanger 1130. When system 1100 is operating, the fuel in the core region 1116 can heat and vaporize the fluid in the heat pipes within the heat pipe layer 1111, and the fluid can transfer heat to the heat exchanger 1130. The heat pipes within the heat pipe layer 1111 can then return the fluid towards the core region 1116 by suction, gravity, and / or other means of heating and vaporizing it again.
[0093] In some embodiments, the heat exchanger 1130 may be analogous to the steam generator 1030 in Figure 10 and may include, for example, one or more helical coil tubes winding around a heat pipe layer 1111. The tubes of the heat exchanger 1130 contain or can contain a working fluid (a coolant such as water or another fluid) that transports heat from the heat pipe layer 1111 to the outside of the furnace vessel 1120 and containment vessel 1110 for use in generating electricity, steam, and / or the like. For example, in the illustrated embodiment, the heat exchanger 1130 is operably connected to a turbine 1143, a generator 1144, a condenser 1145, and a pump 1146. As the temperature of the working fluid in the heat exchanger 1130 increases, the working fluid may begin to boil and vaporize. The vaporized working fluid (e.g., steam) may be used to drive the turbine 1143 and convert the thermal potential energy of the working fluid into electrical energy via the generator 1144. The condenser 1145 can condense the working fluid after it has passed through the turbine 1143, and the pump 1146 can direct the working fluid back to the heat exchanger 1130, where the working fluid can initiate another thermal cycle. In other embodiments, the steam from the heat exchanger 1130 can be routed for direct use in industrial processes, such as enhanced oil recovery operations, which are described in detail below. Thus, the steam exiting the heat exchanger 1130 can bypass the turbine 1143, generator 1144, condenser 1145, pump 1146, etc.
[0094] Figure 12 is a schematic diagram of a nuclear power plant system 1250 including a plurality of reactors 1200 according to an embodiment of the present technology. Each of the reactors 1200 (each individually identified as the 1st to 12th reactors 1200a to l) is similar to and / or identical to the reactors 1200 described in detail above with reference to Figures 10 and 11. The power plant system 1250 ("power plant system 1250") can be "modular" in that each of the reactors 1200 can operate independently to provide output such as electricity or steam. The power plant system 1250 may include fewer than 12 reactors 1200 (e.g., 2, 3, 4, 5, 6, 7, 8, 9, 10, or 11 reactors 1200) or more than 12 reactors 1200. The power plant system 1250 may be a permanent installation or it may be mobile (e.g., mounted on a truck, tractor, mobile platform, and / or similar). In the illustrated embodiment, each of the reactors 1200 may be located in a common housing 1251, such as a reactor plant building, and may be controlled and / or monitored via a control room 1252.
[0095] Each reactor 1200 can be connected to a corresponding power conversion system 1240 (each individually identified as the first to twelfth power conversion systems 1240a to l). The power conversion system 1240 may include one or more devices that generate electricity or any other form of usable electricity from the steam generated by the reactor 1200. In some embodiments, multiple reactors 1200 can be connected to the same power conversion system 1240, and / or one or more reactors 1200 can be connected to multiple power conversion systems 1240 such that there is no one-to-one correspondence between the reactors 1200 and the power conversion systems 1240.
[0096] The power conversion system 1240 can be further connected to a power transmission system 1254, for example, via a power bus 1253. The power transmission system 1254 and / or power bus 1253 may include one or more transmission lines, transformers, and / or similar devices for regulating the current, voltage, and / or other characteristics of the electricity generated by the power conversion system 1240. The power transmission system 454 can route electricity to one or more end uses, such as different electrical loads of an integrated energy system, via multiple electrical output paths 1255 (individually identified as electrical output paths 1255a-n).
[0097] Each of the reactors 1200 can be further connected to a steam transmission system 1256, for example, via a steam bus 1257. The steam bus 1257 can route steam generated from the reactors 1200 to the steam transmission system 1256, which can then route the steam to one or more end uses, such as different steam inputs in an integrated energy system, via a plurality of steam output paths 1258 (individually identified as steam output paths 1258a to n).
[0098] In some embodiments, the reactor 1200 can be individually controlled (e.g., via a control room 1252) to supply steam to a steam transmission system 1256 and / or to a corresponding power conversion system 1240 to supply electricity to a power transmission system 1254. In some embodiments, the reactor 1200 is configured to supply steam to either a steam bus 1257 or a corresponding power conversion system 1240, and can switch quickly and efficiently between supplying steam to either. Thus, in some aspects of the art, the reactor 1200 can be controlled modularly and flexibly so that the power plant system 1250 can supply electricity through a power transmission system 1254 and / or steam through a steam transmission system 1256 at different levels / amounts. For example, if the power plant system 1250 is used to supply electricity and steam to one or more industrial processes, such as various components of an integrated energy system, the reactor 1200 can be controlled to meet the different electrical and steam requirements of the industrial processes.
[0099] For example, during a first operating state of an integrated energy system using a power plant system 1250, a first subset of reactors 1200 (e.g., reactors 1 to 6 1200a to f) may be configured to supply steam to a steam transmission system 1256 for use in the first operating state of the integrated energy system, while a second subset of reactors 1200 (e.g., reactors 7 to 12 1200g to l) may be configured to supply steam to a corresponding power conversion system 1240 (e.g., power conversion systems 7 to 12 1240g to l) to generate electricity for the first operating state of the integrated energy system. Subsequently, during a second operating state of the integrated energy system where different (e.g., more or less) amounts of steam and / or electricity are required, some or all of the first subset of the reactor 1200 can be switched to supply steam to the corresponding power conversion systems 1240 (e.g., power conversion systems 7-12 1240g-l) and / or to supply steam to the steam transmission system 1256, in order to vary the amount of steam and electricity generated to match the requirements / demands of the second operating state. Other variations in steam and electricity generation are possible based on the needs of the integrated energy system. That is, the reactor 1200 can be dynamically / flexibly controlled during other operating states of the integrated energy system to meet the steam and electricity requirements of the operating state.
[0100] In contrast, some conventional nuclear power plant systems can typically generate either steam or electricity for output, and cannot be modularly controlled to provide varying levels of steam and electricity for output. Furthermore, switching between steam and electricity generation is typically difficult (e.g., expensive, time-consuming) in conventional nuclear power plant systems. Specifically, for example, in prototype large-scale nuclear power plant systems, switching between steam and electricity generation is typically extremely time-consuming.
[0101] The reactor 1200 can be individually controlled via one or more operators and / or via a computer system. Therefore, many embodiments of the technology described herein may take the form of computer or machine or controller executable instructions, including routines executed by a programmable computer or controller. Those skilled in the art will understand that this technology can be implemented on computer / controller systems other than those shown and described herein. This technology can be embodied in a special-purpose computer, controller, or data processor that is specifically programmed, configured, or constructed to implement one or more of the computer executable instructions described below. Therefore, the terms “computer” and “controller” as used herein refer to any data processor and may include Internet appliances and handheld devices (including palmtop computers, wearable computers, cellular or mobile phones, multiprocessor systems, processor-based or programmable home electronic devices, network computers, minicomputers, and similar). Information handled by these computers may be presented on any suitable display medium, including liquid crystal displays (LCDs).
[0102] This technology can also be implemented in a distributed environment in which tasks or modules are performed by remote processing devices linked through a communication network. In a distributed computing environment, program modules or subroutines may reside in local and remote memory storage devices. Embodiments of the technology described herein may be stored or distributed on computer-readable media, including magnetically or optically readable or removable computer disks, and may be electronically distributed over a network. Specific data structures and data transmissions for embodiments of this technology are also included within the scope of the embodiments of the technology.
[0103] Exemplary clause The following paragraphs describe various examples. Any of the examples in this section may be used in conjunction with any of the other examples in this section and / or any other examples or embodiments described herein.
[0104] A. A containment isolation system comprising a containment vessel, a first containment isolation valve downstream of the containment vessel, a second containment isolation valve downstream of the first containment isolation valve, and a test valve upstream of the first containment isolation valve and downstream of the containment vessel, wherein the test valve comprises a body, a disk disposed within the body, the disk being configured to receive a key and to be rotated by the key before and after a test operation is performed using at least one of the first containment isolation valve or the second containment isolation valve, and the disk being configured to rotate with the key, and a cover connected to the body, the cover being configured to be removed before the key is inserted in order to allow the key to be inserted into and rotated on the disk.
[0105] B. The storage isolation system according to paragraph A, wherein the cover includes at least one of a position indicator or a flow indicator.
[0106] C. The containment isolation system according to paragraph A or B, wherein the cover includes a test port configured to provide a fluid passage through the cover.
[0107] D. A containment isolation system according to any of paragraphs A to C, wherein the main body includes a test port configured to provide a fluid passage through the main body.
[0108] E. The storage isolation system according to any of paragraphs A to D, further comprising a spindle having a test valve having a first end configured to engage with a cover and a second end opposite to the first end configured to engage with a disk.
[0109] F. A storage isolation system according to any of paragraphs A to E, comprising a spindle configured to extend within the main body.
[0110] G. A storage isolation system according to any of paragraphs A to F, comprising a spindle configured to engage with a disk.
[0111] H. An integrated system comprising a reactor, a containment isolation system, a containment isolation test valve including a containment isolation test valve having a test port configured to receive pressurized fluid and a test port plug configured to rotate to seal the test port, and a containment isolation valve downstream of the containment isolation test valve having a containment isolation valve configured to restrict fluid flow through a disk and seat assembly disposed within the containment isolation valve.
[0112] I. The storage isolation system according to paragraph H, wherein the storage isolation test valve is a first storage isolation test valve, and the integrated system further comprises a second storage isolation test valve.
[0113] J. The containment isolation system according to paragraph H or I, wherein the containment isolation test valve includes a cover, the cover having at least one of a position indicator or a flow indicator.
[0114] K. A storage isolation system according to any of paragraphs H to J, wherein the test port is a first test port, the test port plug is a first test port plug, and the storage isolation valve further includes a cover, the cover being configured to provide a fluid passage through the cover, and the second test port plug being configured to rotate to seal the second test port.
[0115] L. The storage isolation system according to any of paragraphs H to K, further comprising a spindle having a storage isolation test valve having a first end configured to engage with a cover and a second end opposite to the first end configured to engage with a disk.
[0116] M. The containment isolation system according to any of paragraphs H to L, wherein the containment isolation valve includes a cover having a spindle, and the spindle is configured to extend into the body of the containment isolation valve.
[0117] N. The storage isolation system according to any of paragraphs H to M, wherein the storage isolation valve includes a cover having a spindle configured to engage with a disk, and the disk is disposed within the body of the storage isolation test valve.
[0118] O. An isolation test valve comprising: a body having a first test port configured to receive pressurized fluid; a first test port plug configured to rotate to seal the first test port; a disk disposed within the body, the disk configured to receive a working tool and to be rotated by the working tool before and after performing an isolation test operation, and the disk configured to rotate together with the working tool; a cover configured to be connected to the body, the cover including a second test port configured to receive pressurized fluid and a second test port plug configured to rotate to seal the second test port; a first seal disposed between the cover and the body, the first seal disposed adjacent to the first side of the second test port; and a second seal disposed between the cover and the body, the second seal disposed adjacent to the second side of the second test port, the second side of the second test port being opposite to the first side of the second test port.
[0119] The storage isolation system according to paragraph O, wherein the cover includes at least one of a position indicator or a flow indicator.
[0120] Q. The containment isolation system according to paragraph O or P, wherein the cover includes a spindle configured to extend into the body of the isolation test valve.
[0121] A storage isolation system according to any of paragraphs O to Q, comprising a spindle configured to engage with a disk.
[0122] The storage isolation system according to any of paragraphs O to R, further comprising a spindle having an isolation test valve having a first end configured to engage with a cover and a second end opposite to the first end configured to engage with a disk.
[0123] T. A storage isolation system as described in any of paragraphs O to S, wherein the first test port is on the first side of the disk, and the second test port is on the second side of the disk, with the second side being opposite to the first side.
[0124] conclusion While some embodiments have been described using language specific to structural features and / or methodological actions, it should be understood that the claims are not necessarily limited to the specific features or actions described. Rather, the specific features and actions are disclosed as illustrative forms that implement the claimed subject matter. The above descriptions of specific embodiments of the Invention are presented for illustrative and explanatory purposes. They are not intended to be exhaustive or to limit the Invention to the exact forms disclosed, and obviously, many modifications and variations are possible in light of the above teachings. The exemplary embodiments have been selected and described to best illustrate the principles and practical applications of the Invention, thereby enabling those skilled in the art to best utilize the Invention and its various embodiments in various modifications suitable for the particular use intended.
Claims
1. It is a storage and isolation system, Containment vessel and A first containment isolation valve downstream of the containment vessel, A second storage isolation valve downstream of the first storage isolation valve, A test valve located upstream of the first containment isolation valve and downstream of the containment vessel Equipped with, The aforementioned test valve The main unit and A disk disposed within the main body, wherein the disk is configured to receive a key and to be rotated by the key before and after a test operation is performed using at least one of the first or second storage isolation valve, and the disk is configured to rotate together with the key, A cover connected to the main body, wherein the cover is configured to be removed before the key is inserted in order to allow the key to be inserted into the disk and rotated, and A storage and isolation system, including a storage and isolation system.
2. The storage isolation system according to claim 1, wherein the cover includes at least one of a position indicator or a flow indicator.
3. The containment isolation system according to claim 1, wherein the cover includes a test port configured to provide a fluid passage through the cover.
4. The storage and isolation system according to claim 1, wherein the main body includes a test port configured to provide a fluid passage through the main body.
5. The storage isolation system of claim 1, further comprising a spindle having a test valve configured to engage with the cover and a second end opposite to the first end configured to engage with a disk.
6. The storage and isolation system according to claim 1, wherein the cover includes a spindle configured to extend within the main body.
7. The storage isolation system according to claim 1, wherein the cover includes a spindle configured to engage with the disk.
8. It is an integrated system, Nuclear reactor and Storage and isolation system Equipped with, The aforementioned storage and isolation system, A retractable isolation test valve, A test port configured to receive pressurized fluid, A retractable isolation test valve, including a test port plug configured to rotate to seal the test port, A storage isolation valve downstream of the storage isolation test valve, configured to restrict fluid flow through a disk and seat assembly disposed within the storage isolation valve, and An integrated system that includes this.
9. The aforementioned retraction isolation test valve is the first retraction isolation test valve, The integrated system according to claim 8, further comprising a second storage isolation test valve.
10. The integrated system of claim 8, wherein the retractable isolation test valve includes a cover, and the cover has at least one of a position indicator or a flow indicator.
11. The aforementioned test port is the first test port, The aforementioned test port plug is the first test port plug, The aforementioned retractable isolation valve further includes a cover, The aforementioned cover, A second test port is configured to provide a fluid passage through the cover, A second test port plug configured to rotate to seal the second test port, and The integrated system of claim 8, including the above.
12. The aforementioned retractable isolation test valve further includes a spindle, The aforementioned spindle A first end configured to engage with the cover, The second end opposite the first end is configured to engage with the disk and The integrated system of claim 8, having the following features.
13. The aforementioned storage isolation valve includes a cover having a spindle, The integrated system of claim 8, wherein the spindle is configured to extend within the body of the storage isolation valve.
14. The storage isolation valve includes a cover having a spindle configured to engage with a disk, The integrated system of claim 8, wherein the disk is disposed within the body of the storage isolation test valve.
15. It is an isolation test valve, A body having a first test port configured to receive pressurized fluid, A first test port plug configured to rotate to seal the first test port, A disk disposed within the main body, wherein the disk is configured to receive an operating tool and be rotated by the operating tool before and after performing an isolation test operation, and the disk is configured to rotate together with the operating tool, A cover configured to be connected to the main body, the cover including a second test port configured to receive the pressurized fluid, and a second test port plug configured to rotate to seal the second test port, A first seal disposed between the cover and the main body, wherein the first seal is disposed adjacent to the first side of the second test port, A second seal disposed between the cover and the main body, wherein the second seal is disposed adjacent to the second side of the second test port, and the second side of the second test port is opposite to the first side of the second test port. Includes isolation test valves.
16. The isolation test valve according to claim 15, wherein the cover includes at least one of a position indicator or a flow indicator.
17. The isolation test valve according to claim 15, wherein the cover includes a spindle configured to extend into the body of the isolation test valve.
18. The isolation test valve of claim 15, wherein the cover includes a spindle configured to engage with the disk.
19. The isolation test valve further includes a spindle, The aforementioned spindle A first end configured to engage with the cover, The second end opposite to the first end is configured to engage with the disk. An isolation test valve according to claim 15, having the following:
20. The first test port is located on the first side of the disk, The second test port is located on the second side of the disk, The isolation test valve according to claim 15, wherein the second side is opposite to the first side.
Citation Information
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