A test method for a magnetic confinement fusion reactor deuterium-tritium internal fuel circulation demonstration experiment system

Abstract

The application discloses a test method of a magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experiment system, and relates to the field of nuclear fuel.The method formulates three typical operation modes of a demonstration system according to a 500MW magnetic confinement fusion reactor plasma pulse discharge mode, compiles three automatic control programs, and details test steps, test methods, key test parameter acquisition methods and test qualification judgment conditions of each operation mode.Through the method, experimental data of hydrogen isotope processing rate, product gas purity and recovery efficiency of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle system under different operation modes can be obtained, which provides important support for engineering design of a tritium factory system of a magnetic confinement fusion device in China.

Description

Technical Field

[0001] This invention relates to the field of nuclear fuel, specifically to a test method for a demonstration experimental system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor. Background Technology

[0002] The statements in this section are provided only as background information in relation to this disclosure and may not constitute prior art.

[0003] Nuclear fusion energy, with its abundant resources, environmental friendliness, and inherent safety, is poised to become an ideal energy source for the future of human society and one of the ultimate solutions to energy and environmental problems. The generation of fusion energy primarily relies on the fusion of hydrogen isotopes deuterium (D) and tritium (T) (D + T → n(14.06 MeV) + 4He(3.52 MeV)). Because the deuterium-tritium burnup in magnetic confinement fusion reactors is less than 5%, and impurities such as 4He and H2 gradually increase with the fusion reaction, leading to a decrease in fusion reaction efficiency, the "burned" gas must be continuously removed from the fusion reactor vacuum chamber to maintain operation. This process is called ash removal, and the system that recovers tritium from the plasma ash removal gas is called the fusion reactor deuterium-tritium internal fuel cycle system. For a 500MW fusion reactor, the throughput of tritium circulation can reach the kilogram level per hour. How to achieve efficient and safe recycling of tritium on such a scale, so as to achieve tritium "self-sufficiency", is a global challenge in the field of fusion today.

[0004] Most existing fusion reactor internal fuel cycle subsystems (TEP, ISS, and SDS) are not fully integrated, lack automated control, and have a small processing scale. They can only conduct unit system tests and have not established complete test methods for the plasma pulse discharge mode of 500MW-class fusion reactors. They cannot simulate various operating modes of fusion reactor plasma ash removal, nor can they obtain important test data such as hydrogen isotope processing rate and recovery efficiency under different operating modes. Summary of the Invention

[0005] The purpose of this invention is to address the aforementioned problems. Based on the design and construction of a demonstration experimental system for deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor disclosed in Chinese Patent Application No. CN110797127A, and according to the plasma pulse discharge mode of a 500MW-class fusion reactor, this invention proposes an experimental method for a demonstration experimental system for deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor. This method utilizes DCS automatic control technology to automatically adjust the operating parameters of the deuterium-tritium internal fuel cycle demonstration experimental system for the plasma pulse discharge mode of a 500MW-class fusion reactor, conducting hydrogen isotope cycling process experiments under different operating scenarios. It obtains experimental data such as hydrogen isotope processing rate and recovery efficiency under different operating modes, laying a solid foundation for the engineering design of tritium factory systems for magnetic confinement fusion devices in my country, thereby solving the aforementioned problems.

[0006] The technical solution of the present invention is as follows:

[0007] A test method for a demonstration system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor includes:

[0008] Based on the demonstration experimental system of deuterium-tritium internal fuel cycle in magnetic confinement fusion reactor, multiple operating modes were established, and DCS automatic control technology was used to program each operating mode to realize the automatic control of various operating modes and the real-time storage of experimental data.

[0009] Based on each operating mode, corresponding experimental methods were developed, and experimental data of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system under different operating modes were obtained through experiments, providing important support for the engineering design of the tritium factory system of the magnetic confinement fusion device.

[0010] Furthermore, the various operating modes include the following three:

[0011] The system includes three operating modes: rapid operation mode for ash exhaust gas treatment, continuous operation mode for full-process ash exhaust gas treatment, and centralized isotope deproium removal operation mode.

[0012] Furthermore, the program for each operating mode is developed using DCS automatic control technology, including:

[0013] For the three operating modes of the deuterium-tritium fuel cycle demonstration experimental system of the magnetic confinement fusion reactor, three sets of programs were developed using DCS automatic control technology: "Automatic Control for Rapid Operation of Ash Gas Treatment", "Automatic Control for Continuous Treatment of Ash Gas Throughout the Entire Process", and "Automatic Control for Centralized Isotope Deproium Removal".

[0014] Furthermore, the rapid operation mode for treating the ash exhaust gas includes:

[0015] The SDS system and TEP system were tested together. The exhaust gas after being processed by the TEP system was sent directly to the SDS system without being processed by the ISS system. This was used to simulate the rapid operation mode of plasma exhaust gas treatment in the tritium plant of the magnetic confinement fusion reactor, where protium and deuterium were used to simulate deuterium and tritium respectively.

[0016] The continuous ash exhaust gas treatment operation mode includes:

[0017] The SDS system, TEP system, and ISS system were jointly tested and operated. The ISS system's processing capacity can reach 0.5 to 2m. 3 / h range adjustment is used to simulate the plasma ash removal gas treatment operation mode of the tritium plant in a magnetic confinement fusion reactor, where protium and deuterium respectively simulate deuterium and tritium;

[0018] The centralized isotope deprotonation treatment operation mode includes:

[0019] The ISS system has a processing capacity of 5m. 3 / h is used to simulate the centralized deprotonation mode of a tritium plant in a magnetically confined fusion reactor, where deuterium simulates deuterium-tritium.

[0020] Furthermore, the test method for the rapid operation mode of the ash exhaust gas treatment includes:

[0021] Step A: SDS hydrogen isotope gas supply; heating of the SDS system hydrogen deuterium storage bed at 2.4m 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h. 3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h.

[0022] Step B: The gas mixing system prepares the impurity gas; the hydrogen-deuterium mixture is pumped at 2.4 m³ / s using circulating pump C106. 3 A flow rate pump of / h delivers the gas to the gas distribution system. The gas distribution system quickly mixes approximately 5% of impurity gas to simulate ash discharge gas. The content of each impurity gas in the hydrogen isotope after the gas distribution system is mixed is analyzed by a chromatograph and stored in the hydrogen storage tank V101.

[0023] Step C: Hydrogen isotope purification and recovery using the TEP demonstration system; the hydrogen-deuterium mixture containing impurities is pumped through circulation pump C101 at a rate of 2.5 m³ / s. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen and deuterium content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation.

[0024] Furthermore, the experimental method for the continuous treatment operation mode of the entire process ash exhaust gas includes:

[0025] Step 1: The ISS system is running stably; after completing the relevant test preparations, the system cooling and test operation begins, with a maximum feed flow rate of 2m³ / h. 3 / h, the heavy / light component product gases are extracted from the bottom of the first distillation column and the top of the second distillation column, respectively, at flow rates of 0.95m³ / h. 3 / h and 1.05m 3 / h; This process uses low-temperature chromatography to analyze the abundance of isotopes after isotope separation;

[0026] Step 2: The SDS system and TEP system were tested and stabilized; the deuterium hydrogen storage bed of the SDS system was heated to 2.4m. 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h.3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h; the impurity gas is prepared by the gas distribution system; and the hydrogen-deuterium mixture is pumped to the storage tank V107 at a rate of 2.4m³ / h by the circulating pump C106. 3 A flow rate of / h is pumped to the gas distribution system, which rapidly mixes approximately 5% impurity gas to simulate ash discharge. The content of each impurity gas in the hydrogen isotope composition after mixing is analyzed using a chromatograph and stored in hydrogen storage tank V101. The hydrogen-deuterium mixture containing impurity gases is then circulated through pump C101 at a rate of 2.5m³ / h. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen and deuterium content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation.

[0027] Step 3: First phase of full-process joint commissioning of SDS, TEP and ISS systems; After achieving stable operation in Steps 1 and 2, by adjusting the corresponding flow controllers, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation, and the remaining portion is directly sent to the SDS system, thereby realizing the first phase of joint commissioning of SDS, TEP and ISS systems.

[0028] Step 4: Second phase of full-process joint commissioning of SDS, TEP, and ISS systems; After 4 hours of stable operation in the first phase of full-process joint commissioning of SDS, TEP, and ISS systems, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation by adjusting the corresponding flow controllers, and the remaining portion is directly sent to the SDS system, thereby realizing the second phase of joint commissioning of SDS, TEP, and ISS systems;

[0029] Step 5: Third phase of full-process joint commissioning of SDS, TEP, and ISS systems; After 4 hours of stable operation in the second phase of full-process joint commissioning of SDS, TEP, and ISS systems, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation by adjusting the corresponding flow controllers, and the remaining portion is directly sent to the SDS system, thereby realizing the third phase of joint commissioning of SDS, TEP, and ISS systems.

[0030] Furthermore, the experimental method for the centralized isotope deprotonation treatment operation mode includes:

[0031] Step I: SDS system supply; heating the SDS system hydrogen deuterium storage bed assembly at a temperature of not less than 5m. 3A hydrogen-deuterium mixture of 95% D and 5% H was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed using laser Raman spectroscopy. The hydrogen-deuterium mixture was then circulated at a rate of 5 m / h using a C105 circulating pump. 3 The hydrogen is pumped to hydrogen storage tanks V107 to V110 at a rate of / h.

[0032] Step II: ISS System Deproium Removal; To conduct the centralized isotope deproium removal experiment in the ISS system, the ISS system needs to begin all preparatory work before the hydrogen isotope separation experiment; after completing the relevant experimental preparations, the system cooling and test operation will begin, using storage tanks V101 to V104 as raw material gas, and circulating pump C102 to pump the hydrogen-deuterium mixture at a rate of 5m³ / h. 3 The product is pumped to the ISS system at a rate of / h, and the isotope abundance after isotope separation is analyzed by low temperature chromatography. The product gas after isotope separation is then pumped to the SDS system.

[0033] Step III: SDS system receives; SDS system receives at approximately 5m 3 The product gas after de-inflation by the ISS system is received at a rate of / h and stored in a metal hydrogen storage bed for later use.

[0034] Furthermore, the qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the rapid operation mode of ash gas treatment are as follows:

[0035] 1) The TEP system and SDS system were successfully integrated and tested, with a stable operating time of ≥2 hours;

[0036] 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%, hydrogen removal factor ≥10 4 ;

[0037] 3) SDS gas supply speed ≥ 2.4m 3 / h;

[0038] The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the continuous ash gas treatment operation mode are as follows:

[0039] 1) The TEP system, SDS system, and ISS system were integrated for testing, with the ISS system having a processing speed of 2m. 3 Stable operating time ≥ 4h, ISS system processing rate 1m 3 Stable operating time ≥ 4 hours, ISS system processing rate 0.5m / h 3 Stable operating time ≥4h;

[0040] 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%;

[0041] 3) SDS system air supply speed ≥ 2.4m 3 / h;

[0042] 4) The deuterium abundance in the product gas of the ISS system is ≥90%, and the deuterium recovery rate is ≥80%;

[0043] The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium fuel cycle demonstration experiment in the centralized isotope deprotonation treatment operation mode are as follows:

[0044] 1) Hydrogen isotope gas supply rate of SDS system ≥ 5m 3 / h;

[0045] 2) ISS system processing speed ≥ 5m 3 / h, deuterium removal rate ≥80%, deuterium recovery rate ≥95%;

[0046] 3) The hydrogen isotope gas storage rate of the SDS system is ≥5m 3 / h.

[0047] Furthermore, the test data includes:

[0048] TEP system recovery efficiency, TEP system hydrogen removal factor, product gas purity, SDS system gas mixing accuracy, ISS system protium removal rate, and ISS system deuterium recovery rate.

[0049] Furthermore, the recovery efficiency η of the TEP system includes:

[0050] η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)]

[0051] In the formula:

[0052] F1 is the flow rate of the ash discharge gas / raw material gas;

[0053] F3 represents the flow rate of the product gas;

[0054] C1 is the hydrogen concentration in the raw gas for ash removal;

[0055] C2 represents the hydrogen concentration in the exhaust gas;

[0056] C3 represents the hydrogen concentration in the product gas;

[0057] The hydrogen removal factor DF of the TEP system includes:

[0058] DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)]

[0059] In the formula:

[0060] F2 is the exhaust gas flow rate;

[0061] The purity of the product gas is equivalent to the hydrogen isotope concentration in the purified product gas;

[0062] The dehydrogenation rate D of the ISS system includes:

[0063] D=(1-(1-A D2 ) / (1-A D1 ))×100%

[0064] In the formula:

[0065] A D1 The abundance of deuterium in the feed gas;

[0066] A D2 Deuterium abundance in the gaseous component of the recombinant product;

[0067] The deuterium recovery rate of the ISS system includes:

[0068]

[0069] In the formula:

[0070] C0 is the flow rate of the raw gas;

[0071] C1 represents the flow rate of the recombinant component gas.

[0072] Compared with existing technologies, the advantages of this invention are:

[0073] A test method for a demonstration system of deuterium-tritium fuel cycle in a magnetic confinement fusion reactor is presented. Based on the plasma pulse discharge mode of a 500MW-class magnetic confinement fusion reactor, three typical operating modes of the demonstration system are established, and three automated control programs are developed. Detailed test steps, testing methods, key test parameter acquisition methods, and test qualification criteria are provided for each operating mode. This method can obtain experimental data such as hydrogen isotope processing rate, product gas purity, and recovery efficiency under different operating modes of the deuterium-tritium fuel cycle system in a magnetic confinement fusion reactor, providing important support for the engineering design of tritium plant systems in my country's magnetic confinement fusion devices. Attached Figure Description

[0074] Figure 1 A flowchart of the experimental method for a demonstration system of deuterium-tritium fuel cycle in a magnetic confinement fusion reactor;

[0075] Figure 2 This is a schematic diagram of a demonstration experimental system for the internal fuel cycle of a magnetically confined fusion reactor using deuterium and tritium. Detailed Implementation

[0076] It should be noted that relational terms such as "first" and "second" are used merely to distinguish one entity or operation from another, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Furthermore, the terms "comprising," "including," or any other variations thereof are intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Without further limitations, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes said element.

[0077] The features and performance of the present invention will be further described in detail below with reference to embodiments.

[0078] Example 1

[0079] Based on the design and construction of a magnetic confinement fusion reactor deuterium-tritium fuel cycle demonstration experimental system, this embodiment discloses a test method for such a system. This method, based on the plasma pulse discharge mode of a 500MW-class magnetic confinement fusion reactor, establishes three typical operating modes for the demonstration system and develops corresponding automatic control programs for each mode. It also details the test steps, testing methods, key test parameter acquisition methods, and test qualification criteria for each operating mode. This method can obtain experimental data on hydrogen isotope processing rate, product gas purity, and recovery efficiency of the magnetic confinement fusion reactor deuterium-tritium fuel cycle demonstration experimental system under different operating modes, providing important support for the engineering design of tritium plant systems in my country's magnetic confinement fusion devices.

[0080] It should be noted that, as Figure 2 As shown, the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system consists of three major systems: an ash exhaust gas treatment system (TEP system), a hydrogen isotope separation system (ISS system), and a storage and supply system (SDS system), as well as five parts: an analysis and detection system (ANS system) and an auxiliary system. The specific structure and principle can be found in Chinese patent document with publication number CN110797127A.

[0081] Please see Figure 1 A test method for a demonstration experimental system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor, specifically including:

[0082] Based on the demonstration experimental system of deuterium-tritium internal fuel cycle in magnetic confinement fusion reactor, multiple operating modes were established, and DCS automatic control technology was used to program each operating mode to realize the automatic control of various operating modes and the real-time storage of experimental data.

[0083] Based on each operating mode, corresponding experimental methods were developed, and experimental data of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system under different operating modes were obtained through experiments, providing important support for the engineering design of the tritium factory system of the magnetic confinement fusion device.

[0084] In this embodiment, specifically, the multiple operating modes include the following three:

[0085] The system includes three operating modes: rapid operation mode for ash exhaust gas treatment, continuous operation mode for full-process ash exhaust gas treatment, and centralized isotope deproium removal operation mode.

[0086] In this embodiment, specifically, the process of using DCS automatic control technology to program each operating mode includes:

[0087] For the three operating modes of the deuterium-tritium fuel cycle demonstration experimental system of the magnetic confinement fusion reactor, three sets of programs were developed using DCS automatic control technology: "Automatic Control for Rapid Operation of Ash Gas Treatment", "Automatic Control for Continuous Treatment of Ash Gas Throughout the Entire Process", and "Automatic Control for Centralized Isotope Deproium Removal". It should be noted that, based on the three sets of programs, an "Execute" button corresponding to each operating mode can be generated. By clicking the "Execute" button and setting the test parameters for that mode, the test methods can be run automatically by following the steps below.

[0088] In this embodiment, specifically, the rapid operation mode for treating ash exhaust gas includes:

[0089] The SDS system and TEP system were tested together. The exhaust gas after being processed by the TEP system was sent directly to the SDS system without being processed by the ISS system. This was used to simulate the rapid operation mode of plasma exhaust gas treatment in the tritium plant of the magnetic confinement fusion reactor, where protium and deuterium were used to simulate deuterium and tritium respectively.

[0090] The continuous ash exhaust gas treatment operation mode includes:

[0091] The SDS system, TEP system, and ISS system were jointly tested and operated. The ISS system's processing capacity can reach 0.5 to 2m. 3 The range of / h (different operating parameters) is adjusted to simulate the plasma ash removal gas treatment operation mode of the tritium plant in the magnetic confinement fusion reactor, where protium and deuterium respectively simulate deuterium and tritium;

[0092] The centralized isotope deprotonation treatment operation mode includes:

[0093] The ISS system has a processing capacity of 5m. 3 / h, matching the design specifications of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system, is used to simulate the centralized deuterium removal mode of the magnetic confinement fusion reactor tritium plant, where deuterium simulates deuterium-tritium.

[0094] In this embodiment, specifically, the test method for the rapid operation mode of the ash exhaust gas treatment includes:

[0095] Step A: SDS hydrogen isotope gas supply; heating of the SDS system hydrogen (deuterium) storage bed at 2.4m 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h. 3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h.

[0096] Step B: The gas mixing system prepares the impurity gas; the hydrogen-deuterium mixture is pumped at 2.4 m³ / s using circulating pump C106. 3 A flow rate pump of / h delivers the gas to the gas distribution system, which rapidly mixes approximately 5% impurity gas to simulate ash discharge gas. The gas composition is H2~47.5%, D2~47.5%, He~3%, Ne~0.5%, Ar~0.5%, N2~0.5%, CO2~0.23%, CO~0.23%, CH4~0.04%. The content of each impurity gas in the hydrogen isotope after the gas distribution system is prepared is analyzed by a chromatograph and stored in hydrogen storage tank V101.

[0097] Step C: Hydrogen isotope purification and recovery using the TEP demonstration system; the hydrogen-deuterium mixture containing impurities is pumped through circulation pump C101 at a rate of 2.5 m³ / s. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen (deuterium) content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation.

[0098] TEP system recovery efficiency: η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)];

[0099] TEP system hydrogen removal factor: DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)];

[0100] In the formula:

[0101] F1 is the flow rate of the ash discharge gas / raw material gas;

[0102] F3 represents the flow rate of the product gas;

[0103] C1 is the hydrogen concentration in the raw gas for ash removal;

[0104] C2 represents the hydrogen concentration in the exhaust gas;

[0105] C3 represents the hydrogen concentration in the product gas;

[0106] F2 is the exhaust gas flow rate;

[0107] Based on material balance, recovery rate and hydrogen removal factor are only related to concentration;

[0108] Product gas purity: the concentration of hydrogen isotopes in the product gas after purification and recovery;

[0109] It should be noted that the experiment concluded as follows:

[0110] After the SDS system and TEP system have been running stably for 2 hours, the SDS system stops supplying gas to the gas distribution system, and the TEP system continues to purify the hydrogen storage tanks V107 and V101 to the set pressure. Then, the TEP system and SDS system are shut down, and this mode test ends.

[0111] In this embodiment, specifically, the experimental method for the continuous treatment operation mode of the entire process ash exhaust gas includes:

[0112] Step 1: The ISS system is running stably; after completing the relevant test preparations, the system cooling and test operation begins, with a maximum feed flow rate of 2m³ / h. 3 / h, the heavy / light component product gases are extracted from the bottom of the first distillation column and the top of the second distillation column, respectively, at flow rates of 0.95m³ / h. 3 / h and 1.05m 3 / h; This process uses low-temperature chromatography to analyze the abundance of isotopes after isotope separation; Preferably, the relevant experimental preparation work includes: before starting the joint test, the ISS system needs to start various preparations for the hydrogen isotope separation test about 20 days in advance, including system pressure holding and leak detection and evacuation and replacement, helium purification treatment and cooling operation of the low-temperature refrigeration system, etc.

[0113] ISS system dehydrogenation rate: D = (1 - (1 - A) / 2) D2 ) / (1-A D1 ))×100%;

[0114] ISS system deuterium recovery rate:

[0115] In the formula:

[0116] A D1 The abundance of deuterium in the feed gas;

[0117] A D2 Deuterium abundance in the gaseous component of the recombinant product;

[0118] C0 is the flow rate of the raw gas;

[0119] C1 is the flow rate of the recombinant component gas;

[0120] Step 2: The SDS system and TEP system are tested and stabilized; SDS hydrogen isotope gas is supplied; the SDS system hydrogen (deuterium) storage bed is heated to 2.4m³. 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h. 3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h.

[0121] The gas distribution system prepares the impurity gas; the hydrogen-deuterium mixture is pumped at 2.4 m³ / s using a circulating pump C106. 3 A flow rate pump of / h delivers the gas to the gas distribution system, which rapidly mixes approximately 5% impurity gas to simulate ash discharge gas. The gas composition is H2~47.5%, D2~47.5%, He~3%, Ne~0.5%, Ar~0.5%, N2~0.5%, CO2~0.23%, CO~0.23%, CH4~0.04%. The content of each impurity gas in the hydrogen isotope after the gas distribution system is prepared is analyzed by a chromatograph and stored in hydrogen storage tank V101.

[0122] The TEP demonstration system purifies and recovers hydrogen isotopes; a hydrogen-deuterium mixture containing impurities is pumped through a circulating pump C101 at a speed of 2.5 m³ / min. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen (deuterium) content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation.

[0123] TEP system recovery efficiency: η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)];

[0124] TEP system hydrogen removal factor: DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)];

[0125] In the formula:

[0126] F1 is the flow rate of the ash discharge gas / raw material gas;

[0127] F3 represents the flow rate of the product gas;

[0128] C1 is the hydrogen concentration in the raw gas for ash removal;

[0129] C2 represents the hydrogen concentration in the exhaust gas;

[0130] C3 represents the hydrogen concentration in the product gas;

[0131] F2 is the exhaust gas flow rate;

[0132] Based on material balance, recovery rate and hydrogen removal factor are only related to concentration;

[0133] Product gas purity: the concentration of hydrogen isotopes in the product gas after purification and recovery;

[0134] Step 3: First phase of full-process joint trial operation of SDS, TEP, and ISS systems; Based on the stable operation achieved in Steps 1 and 2, a portion of the purified hydrogen isotope gas (2m³) from the TEP demonstration system is introduced by adjusting the corresponding flow controllers. 3 The fraction (0.4m) is fed into the ISS system for hydrogen and deuterium isotope separation, while the remaining fraction (0.4m) is sent to the system. 3 / h) is directly fed into the SDS system, thereby realizing the first phase of joint testing of the SDS system, TEP system and ISS system;

[0135] Step 4: Second Phase of Full-Process Joint Trial and Operation of SDS, TEP, and ISS Systems; After 4 hours of stable operation in the first phase of the full-process joint trial and operation of SDS, TEP, and ISS systems, a portion of the purified hydrogen isotope gas (1m³) from the TEP demonstration system is introduced by adjusting the corresponding flow controllers. 3 The fraction (1.4m) is fed into the ISS system for hydrogen and deuterium isotope separation, while the remaining fraction (1.4m) is sent to the system. 3 / h) is directly fed into the SDS system, thereby realizing the second phase of joint testing of the SDS system, TEP system and ISS system;

[0136] Step 5: Third phase of full-process joint commissioning of SDS, TEP, and ISS systems; After 4 hours of stable operation in the second phase of the full-process joint commissioning of SDS, TEP, and ISS systems, a portion of the purified hydrogen isotope gas (0.5m³) from the TEP demonstration system is introduced by adjusting the corresponding flow controllers. 3 The fraction (1.9m) is fed into the ISS system for hydrogen and deuterium isotope separation, while the remaining fraction (1.9m) is sent to the system. 3 / h) is directly fed into the SDS system, thereby realizing the third-stage joint test of the SDS system, TEP system and ISS system;

[0137] Preferably, in this step, the hydrogen isotope abundance after SDS system preparation is analyzed by laser Raman spectroscopy, the hydrogen (deuterium) content in impurity gas after TEP system purification is analyzed by chromatographic inspection instrument, and the isotope abundance after isotope separation in ISS system is analyzed by low temperature chromatography.

[0138] TEP system recovery efficiency: η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)];

[0139] TEP system hydrogen removal factor: DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)];

[0140] In the formula:

[0141] F1 is the flow rate of the ash discharge gas / raw material gas;

[0142] F3 represents the flow rate of the product gas;

[0143] C1 is the hydrogen concentration in the raw gas for ash removal;

[0144] C2 represents the hydrogen concentration in the exhaust gas;

[0145] C3 represents the hydrogen concentration in the product gas;

[0146] F2 is the exhaust gas flow rate;

[0147] Based on material balance, recovery rate and hydrogen removal factor are only related to concentration;

[0148] Product gas purity: the concentration of hydrogen isotopes in the product gas after purification and recovery;

[0149] ISS system dehydrogenation rate: D = (1 - (1 - A) / 2) D2 ) / (1-A D1 ))×100%;

[0150] ISS system deuterium recovery rate:

[0151] In the formula:

[0152] A D1 The abundance of deuterium in the feed gas;

[0153] A D2 Deuterium abundance in the gaseous component of the recombinant product;

[0154] C0 is the flow rate of the raw gas;

[0155] C1 is the flow rate of the recombinant component gas;

[0156] It should be noted that the experiment concluded as follows:

[0157] After completing the above five steps, first switch the ISS system to independent operation mode, then shut down the TEP system and SDS system according to the ash exhaust gas rapid operation mode, and finally shut down the ISS system to end this mode test.

[0158] In this embodiment, specifically, the experimental method for the centralized isotope deprotonation treatment operation mode includes:

[0159] Step I: SDS system supply; heating the SDS system hydrogen (deuterium) storage bed assembly at a temperature of not less than 5m. 3 A hydrogen-deuterium mixture of 95% D and 5% H was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed using laser Raman spectroscopy. The hydrogen-deuterium mixture was then circulated at a rate of 5 m / h using a C105 circulating pump. 3 The hydrogen is pumped to hydrogen storage tanks V107 to V110 at a rate of / h.

[0160] Step II: ISS System Deproium Removal; To conduct the centralized isotope deproium removal experiment of the ISS system, the ISS system needs to begin all preparatory work before the hydrogen isotope separation experiment; after completing the relevant experimental preparations, the system cooling and test operation will begin, using storage tanks V101 to V104 as raw material gas, and circulating pump C102 to pump the hydrogen-deuterium mixture (95% D, 5% H) at a rate of 5m³ / min. 3 The product gas is pumped to the ISS system at a rate of / h, and the isotope abundance after isotope separation is analyzed by low-temperature chromatography. The product gas after isotope separation is then pumped to the SDS system. Preferably, the preparation work in each direction includes: the ISS system needs to undergo impurity removal treatment of raw material hydrogen isotope gas about 20 days in advance, system pressure holding and leak detection and evacuation and replacement, and helium purification treatment and cooling operation of the low-temperature refrigeration system.

[0161] ISS system dehydrogenation rate: D = (1 - (1 - A) / 2) D2 ) / (1-A D1 ))×100%;

[0162] ISS system deuterium recovery rate:

[0163] Step III: SDS system receives; SDS system receives at approximately 5m 3 The product gas after de-protonation by the ISS system is received at a rate of / h and stored in a metal hydrogen storage bed for later use.

[0164] In this embodiment, the qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the rapid operation mode of ash gas treatment are as follows:

[0165] 1) The TEP system and SDS system were successfully integrated and tested, with a stable operating time of ≥2 hours;

[0166] 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%, hydrogen removal factor ≥10 4 ;

[0167] 3) SDS gas supply speed ≥ 2.4m3 / h;

[0168] The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the continuous ash gas treatment operation mode are as follows:

[0169] 1) The TEP system, SDS system, and ISS system were integrated for testing, with the ISS system having a processing speed of 2m. 3 Stable operating time ≥ 4h, ISS system processing rate 1m 3 Stable operating time ≥ 4 hours, ISS system processing rate 0.5m / h 3 Stable operating time ≥4h;

[0170] 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%;

[0171] 3) SDS system air supply speed ≥ 2.4m 3 / h;

[0172] 4) The deuterium abundance in the product gas of the ISS system is ≥90%, and the deuterium recovery rate is ≥80%;

[0173] The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium fuel cycle demonstration experiment in the centralized isotope deprotonation treatment operation mode are as follows:

[0174] 1) Hydrogen isotope gas supply rate of SDS system ≥ 5m 3 / h;

[0175] 2) ISS system processing speed ≥ 5m 3 / h, deuterium removal rate ≥80%, deuterium recovery rate ≥95%;

[0176] 3) The hydrogen isotope gas storage rate of the SDS system is ≥5m 3 / h.

[0177] In this embodiment, the multi-mode operation experimental parameters of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system include:

[0178] TEP system recovery efficiency, TEP system hydrogen removal factor, product gas purity, ISS system protium removal rate, and ISS system deuterium recovery rate.

[0179] In this embodiment, the specific method for obtaining experimental parameters for the multi-mode operation of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system is as follows:

[0180] The recovery efficiency η of the TEP system includes:

[0181] η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)]

[0182] In the formula:

[0183] F1 is the flow rate of the ash discharge gas / raw material gas;

[0184] F3 represents the flow rate of the product gas;

[0185] C1 is the hydrogen concentration in the raw gas for ash removal;

[0186] C2 represents the hydrogen concentration in the exhaust gas;

[0187] C3 represents the hydrogen concentration in the product gas;

[0188] The hydrogen removal factor DF of the TEP system includes:

[0189] DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)]

[0190] In the formula:

[0191] F2 is the exhaust gas flow rate;

[0192] The purity of the product gas is equivalent to the hydrogen isotope concentration in the purified product gas;

[0193] The dehydrogenation rate D of the ISS system includes:

[0194] D=(1-(1-A D2 ) / (1-A D1 ))×100%

[0195] In the formula:

[0196] A D1 The abundance of deuterium in the feed gas;

[0197] A D2 Deuterium abundance in the gaseous component of the recombinant product;

[0198] The deuterium recovery rate of the ISS system includes:

[0199]

[0200] In the formula:

[0201] C0 is the flow rate of the raw gas;

[0202] C1 represents the flow rate of the recombinant component gas.

[0203] The embodiments described above merely illustrate specific implementation methods of this application, and while the descriptions are detailed and specific, they should not be construed as limiting the scope of protection of this application. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of the technical solution of this application, and these modifications and improvements all fall within the scope of protection of this application.

[0204] This background section is provided to generally present the context of the invention. The work of the currently named inventors, the work to the extent described in this background section, and aspects described in this section that did not constitute prior art at the time of application are neither expressly nor impliedly acknowledged as prior art to the invention.

Claims

1. A test method for a demonstration experimental system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor, characterized in that, include: Based on the demonstration experimental system of deuterium-tritium internal fuel cycle in magnetic confinement fusion reactor, multiple operating modes were established, and DCS automatic control technology was used to program each operating mode to realize the automatic control of various operating modes. Based on each operating mode, corresponding test methods were developed, and test data of the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system under different operating modes were obtained through experiments, providing important support for the engineering design of the tritium factory system of the magnetic confinement fusion device. The various operating modes include the following three: Ash exhaust gas treatment rapid operation mode, full-process ash exhaust gas continuous operation mode, centralized isotope deproium removal operation mode; The rapid operation mode for ash exhaust gas treatment includes: The SDS system and TEP system were tested together. The exhaust gas after being processed by the TEP system was sent directly to the SDS system without being processed by the ISS system. This was used to simulate the rapid operation mode of plasma exhaust gas treatment in the tritium plant of the magnetic confinement fusion reactor, where protium and deuterium were used to simulate deuterium and tritium respectively. The continuous ash exhaust gas treatment operation mode includes: The SDS system, TEP system, and ISS system were jointly tested and operated. The ISS system's processing capacity can reach 0.5~2m. 3 / h range adjustment is used to simulate the plasma ash removal gas treatment operation mode of the tritium plant in a magnetic confinement fusion reactor, where protium and deuterium respectively simulate deuterium and tritium; The centralized isotope deprotonation treatment operation mode includes: The ISS system has a processing capacity of 5m. 3 / h is used to simulate the centralized deprotonation mode of a tritium plant in a magnetically confined fusion reactor, where deuterium simulates deuterium-tritium; The experimental method for the continuous treatment operation mode of the entire process of ash exhaust gas includes: Step 1: The ISS system is running stably; after completing the relevant test preparations, the system cooling and test operation begins, with a maximum feed flow rate of 2m³ / h. 3 / h, the heavy / light component product gases are extracted from the bottom of the first distillation column and the top of the second distillation column, respectively, at flow rates of 0.95m³ / h. 3 / h and 1.05m 3 / h; This process uses low-temperature chromatography to analyze the abundance of isotopes after isotope separation; Step 2: The SDS system and TEP system were tested and stabilized; the deuterium hydrogen storage bed of the SDS system was heated to 2.4m. 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h. 3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h; the impurity gas is prepared by the gas distribution system; and the hydrogen-deuterium mixture is pumped to the storage tank V107 at a rate of 2.4m³ / h by the circulating pump C106. 3 A flow rate of / h is pumped to the gas distribution system, which rapidly mixes approximately 5% impurity gas to simulate ash discharge. The content of each impurity gas in the hydrogen isotope composition after mixing is analyzed using a chromatograph and stored in hydrogen storage tank V101. The hydrogen-deuterium mixture containing impurity gases is then circulated through pump C101 at a rate of 2.5m³ / h. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen and deuterium content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation. Step 3: First phase of full-process joint commissioning of SDS, TEP and ISS systems; After achieving stable operation in Steps 1 and 2, by adjusting the corresponding flow controllers, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation, and the remaining portion is directly sent to the SDS system, thereby realizing the first phase of joint commissioning of SDS, TEP and ISS systems. Step 4: Second phase of full-process joint commissioning of SDS, TEP, and ISS systems; After 4 hours of stable operation in the first phase of full-process joint commissioning of SDS, TEP, and ISS systems, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation by adjusting the corresponding flow controllers, and the remaining portion is directly sent to the SDS system, thereby realizing the second phase of joint commissioning of SDS, TEP, and ISS systems; Step 5: Third phase of full-process joint commissioning of SDS, TEP and ISS systems; After 4 hours of stable operation in the second phase of full-process joint commissioning of SDS, TEP and ISS systems, a portion of the hydrogen isotope gas purified and removed by the TEP demonstration system is sent to the ISS system for hydrogen-deuterium isotope separation by adjusting the corresponding flow controller, and the remaining portion is directly sent to the SDS system, thereby realizing the third phase of joint commissioning of SDS, TEP and ISS systems; The test method for the rapid operation mode of the ash exhaust gas treatment includes: Step A: SDS hydrogen isotope gas supply; heating of the SDS system hydrogen deuterium storage bed at 2.4m 3 A 1:1 hydrogen-deuterium mixture was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed every 10 minutes using a laser Raman spectrometer. The hydrogen-deuterium mixture was also supplied via a C105 circulating pump at a flow rate of 2.4 m³ / h. 3 The hydrogen is pumped to the hydrogen storage tank V107 at a rate of / h. Step B: The gas mixing system prepares the impurity gas; the hydrogen-deuterium mixture is pumped at 2.4 m³ / s using circulating pump C106. 3 A flow rate pump of / h delivers the gas to the gas distribution system. The gas distribution system quickly mixes approximately 5% of the impurity gas to simulate ash discharge gas. The content of each impurity gas in the hydrogen isotope after the gas distribution system is mixed is analyzed by a chromatograph and stored in the hydrogen storage tank V101. Step C: Hydrogen isotope purification and recovery using the TEP demonstration system; the hydrogen-deuterium mixture containing impurities is pumped through circulation pump C101 at a rate of 2.5 m³ / s. 3 A flow rate of / h is pumped to the TEP system, and the hydrogen and deuterium content in the purified impurity gas is analyzed by a chromatograph. The gas processed by the TEP system is directly returned to the SDS system, thereby achieving stable cyclic operation. The experimental method for the centralized isotope deprotonation treatment operation mode includes: Step I: SDS system supply; heating the SDS system hydrogen deuterium storage bed assembly at a temperature of not less than 5m. 3 A hydrogen-deuterium mixture with 95% D and 5% H was supplied at a flow rate of / h. The hydrogen isotope abundance prepared by the SDS system was analyzed using laser Raman spectroscopy. The hydrogen-deuterium mixture was then circulated at a rate of 5 m / h using a C105 circulating pump. 3 The hydrogen is pumped to hydrogen storage tanks V107~V110 at a rate of / h; Step II: ISS System Deproium Removal; To conduct the centralized isotope deproium removal experiment on the ISS system, the ISS system needs to begin all preparatory work before the hydrogen isotope separation experiment; after completing the relevant experimental preparations, the system cooling and test operation will begin, using storage tanks V101~V104 as raw material gas, and circulating pump C102 will pump the hydrogen-deuterium mixture at a rate of 5m³ / h. 3 The product is pumped to the ISS system at a rate of / h, and the isotope abundance after isotope separation is analyzed by low temperature chromatography. The product gas after isotope separation is then pumped to the SDS system. Step III: SDS system receives; SDS system receives at approximately 5m 3 The product gas after de-inflation by the ISS system is received at a rate of / h and stored in a metal hydrogen storage bed for later use.

2. The experimental method for a demonstration system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor according to claim 1, characterized in that, The program for each operating mode is developed using DCS automatic control technology, including: For the three operating modes of the deuterium-tritium fuel cycle demonstration experimental system of the magnetic confinement fusion reactor, three sets of programs were developed using DCS automatic control technology: "Automatic Control for Rapid Operation of Ash Gas Treatment", "Automatic Control for Continuous Treatment of Ash Gas Throughout the Entire Process", and "Automatic Control for Centralized Isotope Deproium Removal".

3. The experimental method for a demonstration system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor according to claim 2, characterized in that, The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the rapid operation mode of ash gas treatment are as follows: 1) The TEP system and SDS system were successfully integrated and tested, with a stable operating time of ≥2 hours; 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%, hydrogen removal factor ≥10 4 ; 3) SDS gas supply speed ≥ 2.4m 3 / h; The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium internal fuel cycle demonstration experimental system in the continuous ash gas treatment operation mode are as follows: 1) The TEP system, SDS system, and ISS system were integrated for testing, with the ISS system having a processing speed of 2m. 3 Stable operating time ≥ 4h, ISS system processing rate 1m 3 Stable operating time ≥ 4 hours, ISS system processing rate 0.5m / h 3 Stable operating time ≥4h; 2) TEP system processing rate ≥ 2.5m 3 / h, hydrogen isotope recovery efficiency ≥99%; 3) SDS system air supply speed ≥ 2.4m 3 / h; 4) The deuterium abundance in the product gas of the ISS system is ≥90%, and the deuterium recovery rate is ≥80%; The qualification criteria for the magnetic confinement fusion reactor deuterium-tritium fuel cycle demonstration experiment in the centralized isotope deprotonation treatment operation mode are as follows: 1) Hydrogen isotope gas supply rate of SDS system ≥ 5m 3 / h; 2) ISS system processing speed ≥ 5m 3 / h, deuterium removal rate ≥80%, deuterium recovery rate ≥95%; 3) The hydrogen isotope gas storage rate of the SDS system is ≥5m 3 / h.

4. The experimental method for a demonstration system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor according to claim 3, characterized in that, The test data includes: TEP system recovery efficiency, TEP system hydrogen removal factor, product gas purity, ISS system protium removal rate, and ISS system deuterium recovery rate.

5. The test method for a demonstration experimental system of deuterium-tritium internal fuel cycle in a magnetic confinement fusion reactor according to claim 4, characterized in that, The recovery efficiency η of the TEP system includes: η=(F3×C3) / (F1×C1)=[C3×(C1-C2)] / [C1×(C3-C2)] In the formula: F1 is the flow rate of the ash discharge gas / raw material gas; F3 represents the flow rate of the product gas; C1 is the hydrogen concentration in the raw gas for ash removal; C2 represents the hydrogen concentration in the exhaust gas; C3 represents the hydrogen concentration in the product gas; The hydrogen removal factor DF of the TEP system includes: DF=(F1×C1) / (F2×C2)=[C1×(C3-C2)] / [C2×(C3-C1)] In the formula: F2 is the exhaust gas flow rate; The purity of the product gas is equivalent to the hydrogen isotope concentration in the purified product gas; The ISS system dehydrogenation rate D ,include: In the formula: A D1 The abundance of deuterium in the feed gas; A D2 Deuterium abundance in the gaseous component of the recombinant product; The deuterium recovery rate of the ISS system includes: In the formula: C 0 represents the flow rate of the raw gas; C 1 represents the flow rate of the recombinant component gas.

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