A cold pack with enhanced heat dissipation capabilities, a reactor-based cold neutron source, and a reactor.

By designing a non-nested cold pack structure and coolant cavity, the problems of complex existing cold pack structures and insufficient cooling potential are solved, achieving efficient heat dissipation and improved neutron output capability of the cold pack.

CN120809306BActive Publication Date: 2026-01-30SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE CO LTD
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Patent Information

Application Number
CN202511285411.4
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2025-09-10
Publication Date
2026-01-30
Estimated Expiration
2045-09-10

AI Technical Summary

Technical Problem

The existing reactor-based cold neutron sources have complex cold package structures and insufficient cooling potential, resulting in a lack of room for optimization of neutron output capabilities. Furthermore, some cold neutrons in the moderator cannot be utilized, leading to insufficient heat dissipation.

Method used

A non-nested cold envelope structure is adopted, with the cold envelope cavity and the moderator inlet pipe arranged in parallel. The coolant cavity covers the space between the cold envelope cavity and the inflow section, enhancing the coolant volume ratio. The coolant cavity sleeve promotes coolant flow, and the cross-section of the cold envelope cavity is changed to a fan shape to cover the neutron conduit area.

Benefits of technology

The structure of the cold pack was simplified, the utilization efficiency of the coolant was improved, the heat dissipation capacity of the cold pack was enhanced, and the neutron output capacity and the efficiency and reliability of the cold neutron source were improved.

✦ Generated by Eureka AI based on patent content.

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Abstract

A cold pack with enhanced heat dissipation capacity, a reactor-based cold neutron source, and a reactor belong to the field of nuclear technology. The cold pack with enhanced heat dissipation capacity includes a moderator input pipe, a moderator output pipe, a cold pack cavity, and a coolant circulation loop. The moderator input pipe includes an inflow section and a curved return section. The cold pack cavity is connected to the return section and located on one side of the inflow section, with its maximum cross-section covering the azimuth area of ​​the neutron conduit. The coolant circulation loop includes an input jacket, an output jacket, and a coolant cavity. The coolant cavity encloses the cold pack cavity, the return section, and part of the inflow section, with the space between the cold pack cavity and the inflow section located within the coolant cavity. This cold pack provides a larger volume of coolant for heat dissipation, effectively improving the heat dissipation capacity and cold neutron output efficiency of the cold pack during neutron moderation.
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Description

Technical Field

[0001] This invention belongs to the field of nuclear technology, specifically relating to a cold pack, a reactor-based cold neutron source, and a reactor with enhanced heat dissipation capabilities. Background Technology

[0002] Reactor-based cold neutron sources are currently the most mature and reliable neutron source solutions and are one of the important foundations for the realization of technologies such as neutron scattering. The performance of reactor-based cold neutron sources largely depends on the structural design of the neutron source cold package. Existing reactor-based cold neutron sources generally adopt a nested, thin-walled, irregularly shaped cold package, which is complex. Furthermore, a significant portion of the moderator in the cold package does not actually contribute to neutron output but still generates nuclear heat. Moreover, the nested cold package structure has insufficient cooling potential, resulting in limited room for optimization of the neutron output capability of reactor-based cold neutron sources. Therefore, providing a cold package with enhanced heat dissipation capabilities is of positive significance for optimizing the efficiency and reliability of reactor-based cold neutron sources. Summary of the Invention

[0003] The purpose of this invention is to provide a cold pack with enhanced heat dissipation capabilities, thereby optimizing the efficiency and reliability of reactor-based cold neutron sources. This invention also provides a reactor-based cold neutron source and a reactor.

[0004] According to one embodiment of the present invention, a cooling pack for enhancing heat dissipation is provided. The cooling pack is disposed in a reactor and includes a moderator input pipe, a moderator output pipe, a cooling pack cavity, and a coolant circulation pipeline. The cooling pack cavity is connected between the moderator input pipe and the moderator output pipe.

[0005] The moderator input pipe includes an inflow section and a return section. The inflow section is arranged parallel to the moderator output pipe, and the return section is curved relative to the inflow section.

[0006] The cold envelope cavity is connected to the reflux section, and the cold envelope cavity is located on one side of the inflow section. The maximum cross-section of the cold envelope cavity covers the azimuth range of the neutron conduit arrangement.

[0007] The coolant circulation pipeline includes an input jacket, an output jacket, and a coolant chamber; the coolant chamber covers the cold envelope chamber, the reflux section, and part of the inflow section, such that the space between the cold envelope chamber and the inflow section is within the coolant chamber; the input jacket surrounds the portion of the moderator input pipe located outside the coolant chamber; the output jacket surrounds the portion of the moderator output pipe located outside the coolant chamber.

[0008] The cold pack cavity is located on one side of the moderator inlet section and adopts a non-nested configuration, which reduces the total amount of moderator reacting with thermal neutrons inside the cold pack and lowers the heat generation. By using a coolant cavity to cover the cold pack cavity, the coolant completely fills the gap between the cold pack cavity and the inlet section, increasing the volume ratio of coolant while keeping the volume occupied by the cold pack in the vacuum tube the same, further enhancing the heat dissipation capacity of the cold pack and creating conditions for further improving the cold neutron output capacity of the reactor-based cold neutron source.

[0009] Furthermore, in some embodiments, the shape of the maximum cross-section of the cold cavity is a fan-shaped surface surrounding the inflow section.

[0010] Furthermore, in some embodiments, the cold envelope cavity further includes a lower end cap and an upper end cap, the lower end cap being connected to the reflux section, the upper end cap being connected to the moderator output pipe, and the upper end cap and the lower end cap having a variable cross-section structure.

[0011] Furthermore, in some embodiments, the upper end cap protrudes toward the inflow section.

[0012] Furthermore, in some embodiments, the coolant circulation pipeline further includes a coolant chamber sleeve, which is connected to the input interlayer and extends to the bottom of the coolant chamber. The coolant chamber sleeve has a sleeve opening at its end at the bottom of the coolant chamber, which is the inlet of the coolant in the coolant chamber.

[0013] Furthermore, in some embodiments, the coolant chamber sleeve surrounds the portion of the inflow section within the coolant chamber.

[0014] Furthermore, in some embodiments, the cross-sections of the input interlayer and the inflow section are concentric circles; the cross-sections of the output interlayer and the moderator output pipe are concentric circles.

[0015] According to another aspect of the present invention, a reactor-based cold neutron source is provided, wherein the cold package of the reactor-based cold neutron source adopts the cold package with enhanced heat dissipation capability provided in any of the foregoing embodiments.

[0016] Furthermore, in some embodiments, the reactor-based cold neutron source uses liquid hydrogen or deuterium as a moderator and cryogenic helium as a coolant.

[0017] According to another aspect of the present invention, a reactor is provided in which a reactor-based cold neutron source is provided, wherein the reactor-based cold neutron source is a reactor-based cold neutron source employing a cold pack with enhanced heat dissipation capability in any of the foregoing embodiments. Attached Figure Description

[0018] Figure 1This is a schematic diagram of a cooling pack structure to enhance heat dissipation in one embodiment;

[0019] Figure 2 This is a schematic diagram of the cross-sectional structure of a cooling pack to enhance heat dissipation in one embodiment;

[0020] Figure 3 This is a schematic diagram of a pair of proportional intercooler structures;

[0021] Figure 4 This is a schematic diagram of the cross-sectional structure of a pair of proportional intermediate cooling coils.

[0022] Meaning of the reference numerals in the attached figures:

[0023] 1-Moderator inlet pipe; 11-Inflow section; 12-Return section; 2-Cold packing cavity; 21-Lower end cap; 22-Middle section; 23-Upper end cap; 24-Irregularly shaped cold packing clamping cavity; 3-Moderator outlet pipe; 4-Inlet jacket; 5-Coolant cavity; 51-Coolant cavity sleeve; 52-Sleeve opening; 6-Outlet jacket; 7-Irregularly shaped coolant cavity; 71-Connecting hole; 72-Irregularly shaped coolant cavity inner layer; 73-Irregularly shaped coolant cavity outer layer.

[0024] The purpose of the above-described drawings is to provide a detailed description of the present invention so that those skilled in the art can understand the technical concept of the invention, and is not intended to limit the invention. For the sake of brevity, the above-described drawings only schematically depict the structures related to the technical features of the present invention, and do not depict the complete structure and all details strictly according to actual scale. Detailed Implementation

[0025] The present invention will now be described in further detail with reference to specific embodiments and accompanying drawings.

[0026] The term "embodiment" as used herein means that a particular feature, structure, or characteristic described in connection with an embodiment may be included in at least one embodiment herein. The phrase appearing in various places in the specification does not necessarily refer to the same embodiment, nor is it limited to mutually exclusive, independent, or alternative embodiments. Those skilled in the art will understand that the embodiments herein can be combined with other embodiments without causing structural conflicts.

[0027] In this description, unless otherwise explicitly specified and limited, the technical terms "installation," "connection," "joining," etc., should be interpreted broadly, for example, referring to movable connections, fixed connections, or integration. Those skilled in the art can understand the specific meaning of the above terms in the embodiments of this application based on the specific circumstances.

[0028] In this description, terms such as "upper," "lower," "left," "right," "lateral," "longitudinal," "height," "length," and "width," which indicate orientation or positional relationships, are intended to accurately describe the embodiments and simplify the description, rather than limiting the parts or structures involved to have a specific orientation, or to be installed or operated in a specific orientation, and should not be construed as limiting the embodiments in this document.

[0029] In this description, terms such as "first" and "second" are used only to distinguish different objects and should not be construed as indicating relative importance or limiting the number, specific order, or primary / secondary relationship of the described technical features. In this description, "multiple" means at least two.

[0030] Neutron scattering technology is widely used in industries such as military, energy, semiconductors, and new materials, and the demand is increasing with technological advancements. The foundation of neutron scattering technology is the cold neutron source, and reactor-based cold neutron sources are currently the most stable and reliable cold neutron source solution. The basic principle of a reactor-based cold neutron source is to establish a region containing a cryogenic neutron moderator within the high thermal neutron flux region of the reactor. The cryogenic neutron moderator slows down the thermal neutrons until they reach thermal equilibrium with the moderator, and then transports them outside the reactor via neutron transport systems such as neutron conduits. The main component that contains the cryogenic moderator and reacts with the thermal neutrons is the cold pack of the cold neutron source, and the structure of the cold pack has a crucial impact on the performance and efficiency of the cold neutron source.

[0031] Currently, typical cold package structures for reactor-based cold neutron sources include... Figure 3 and Figure 4 As shown, the system includes a moderator input pipe 1, a cold envelope cavity 2, a moderator output pipe 3, an input interlayer 4, an output interlayer 6, and a shaped coolant cavity 7. The moderator flows into the cold envelope cavity 2 through the moderator input pipe 1. The cold envelope cavity 2 is the main region where the moderator moderates thermal neutrons. Its main body is a shaped cold envelope cavity 24 with an annular cross-section. The spaces inside and outside the shaped cold envelope cavity are connected to form the shaped coolant cavity 7. After the moderator moderates the thermal neutrons in the cold envelope cavity 2, it flows out through the moderator output pipe 3 to the heat exchanger (not shown) of the cold neutron source. After being cooled by the heat exchanger, it flows back through the moderator input pipe 1, achieving a thermosiphon cycle. Because energy exchange occurs during the moderation of thermal neutrons, the deposited nuclei in the moderator generate heat and rise in temperature; therefore, a coolant is needed to cool the moderator. The coolant flows into the inner layer 72 of the irregularly shaped coolant cavity through the input interlayer 4. A connecting hole 71 is provided at the bottom of the irregularly shaped cold pack cavity 24, through which the coolant flows out to the outer layer 73 of the irregularly shaped coolant cavity, and finally out through the output interlayer 6. In this cold pack structure, both the inner and outer surfaces of the irregularly shaped cold pack cavity 24 can be sufficiently cooled by the coolant, allowing the deposited nuclear heat to be effectively dissipated. The interlayer also forms a protective boundary to prevent moderator leakage.

[0032] However, as Figure 4 As shown, the irregularly shaped cold pack cavity 24 has a multi-layered nested structure, which is very complex and difficult to manufacture. At the same time, the cross-section of the irregularly shaped cold pack cavity 24 is annular. Due to structural limitations, the distribution range of the neutron exit tubes cannot cover the entire annular surface. This means that a considerable portion of the cold neutrons moderated by the moderator in the irregularly shaped cold pack cavity 24 cannot be utilized, but their nuclear heat still needs to be cooled by coolant, which increases the heat dissipation pressure. Furthermore, the complex structure of the irregularly shaped cold pack cavity 24 also limits the design optimization of the coolant pipeline, making it difficult to improve the overall heat dissipation capacity of the cold pack by increasing the amount of coolant.

[0033] In order to overcome the above-mentioned problems of the prior art, the present invention provides a cooling pack with enhanced heat dissipation capacity through various embodiments, which can increase the volume ratio of coolant in the cooling pack and improve the heat dissipation capacity of the cooling pack.

[0034] The cold pack structure of the neutron source is as follows: Figure 1 and Figure 2 As shown, it includes a moderator inlet pipe 1, a moderator outlet pipe 3, a cold envelope cavity 2, and a coolant circulation pipeline.

[0035] The moderator input pipe 1 includes an inflow section 11 and a return section 12. The inflow section 11 is arranged parallel to the moderator output pipe 3, while the return section 12 is bent in a U-shape relative to the inflow section 11. The cold envelope 2 is connected to the return section 12 and is located on one side of the inflow section 11. Its cross-sectional area is larger than that of the moderator input pipe 1 and the moderator output pipe 3, forming an enlarged structure. The maximum cross-section of the cold envelope 2 can cover the azimuth range of the neutron conduit arrangement.

[0036] The coolant circulation pipeline includes an input jacket 4, an output jacket 6, and a coolant chamber 5. The coolant chamber 5 covers the cold coil chamber 2, the reflux section 12, and part of the inflow section 11, so that the space between the cold coil chamber 2 and the inflow section is within the coolant chamber 5. The input jacket 4 is a jacketed sleeve that surrounds the portion of the moderator input pipe 1 located outside the coolant chamber 5, and the output jacket 6 is a jacketed sleeve that surrounds the moderator output pipe. In a preferred embodiment, the cross-sections of the input jacket 4 and the moderator input pipe 1 are concentric, and the cross-sections of the output jacket 6 and the moderator output pipe 3 are also concentric.

[0037] In a preferred embodiment, the cold cavity 2 has a middle section 22, which is the part with the largest cross-sectional area of ​​the cold cavity 2, and its cross-sectional shape is a fan-shaped surface arranged around the inflow section 11. The cold cavity 2 also includes an upper end cap 23 disposed at the top and a lower end cap 21 disposed at the bottom. The upper end cap 23 and the lower end cap 21 have gradually changing cross-sectional areas, and the upper end cap 23 protrudes toward the inflow section 11.

[0038] In a further preferred embodiment, the coolant circulation pipeline of the cold pack further includes a coolant chamber sleeve 51. The coolant chamber sleeve 51 is disposed inside the coolant chamber 5, with its upper end connected to the inflow section 11 and its bottom extending to the bottom of the coolant chamber 5 and having a sleeve opening 52. The sleeve opening 52 is the inlet of the coolant in the coolant chamber 5. The coolant flows into the bottom of the coolant chamber 5 from the sleeve opening 52 and enters the output jacket from the top of the coolant chamber 5, flowing back to the radiator. Thermal convection is used to promote sufficient flow of coolant in the coolant chamber and avoid dead zones.

[0039] In this cold pack structure, the cross-sectional shape of the cold pack cavity 2 is replaced by a fan shape instead of the annular shape in the prior art. This simplifies the structure and makes the distribution of the moderator participating in the moderation of thermal neutrons more consistent with the spatial distribution of the neutron conduit. This reduces the volume of the moderator while improving its utilization efficiency. Because the amount of moderator that generates ineffective heat is reduced, the heat dissipation capacity of the cold pack is further optimized. Furthermore, the coolant cavity 5 increases the volume ratio of coolant in the cold pack, resulting in a stronger heat dissipation capacity for the same amount of nuclear heat accumulated in the moderator.

[0040] According to another aspect of the present invention, a reactor-based cold neutron source is provided, comprising a vacuum cylinder, a neutron conduit, a heat exchange device, and a cold pack. The cold pack and heat exchange device are placed inside the vacuum cylinder, wherein the cold pack is an enhanced heat dissipation cold pack provided in any of the foregoing embodiments. This reactor-based cold neutron source uses liquid hydrogen or deuterium as a moderator and cryogenic helium as a coolant. A circulation pipeline is established between the heat exchange device and the cold pack. The coolant flows from outside the reactor into the cooling device for heat exchange and then flows out of the reactor. The moderator flowing out of the cold pack undergoes sufficient heat exchange with the coolant in the cooling device, and after cooling, flows back to the cold pack, thereby ensuring that the cold pack is in a stable cryogenic state. Thermal neutrons are cooled into cold neutrons by the moderator in the cold pack, and are subsequently collected by the neutron conduit and output outside the reactor for use in various neutron experiments utilizing the cold neutron source, such as neutron diffraction.

[0041] Another embodiment of the present invention provides a reactor in which one or more reactor-based cold neutron sources are provided, wherein the reactor-based cold neutron sources are the reactor-based cold neutron sources provided in any of the foregoing embodiments.

[0042] The purpose of the above embodiments is to provide a further detailed description of the present invention in conjunction with the accompanying drawings, so that those skilled in the art can understand the technical concept of the present invention. Within the scope of the present invention, optimization or equivalent substitution of the technical features involved, as well as combination of implementation methods in different embodiments without causing structural and principle conflicts, all fall within the protection scope of the present invention.

Claims

1. A heat dissipation enhanced cold pack arranged in a reactor, comprising a moderator input pipe, a moderator output pipe, a cold pack cavity and a coolant circulation pipeline, the cold pack cavity being connected between the moderator input pipe and the moderator output pipe, characterized in that, the moderator input pipe comprises an inflow section and a reflux section, the inflow section is arranged in parallel with the moderator output pipe, and the reflux section is arranged in a bent manner relative to the inflow section; the cold pack cavity is connected with the reflux section, the cold pack cavity is arranged on one side of the inflow section, a maximum cross section of the cold pack cavity covers an azimuthal interval in which a neutron guide tube is arranged, the cold pack cavity further comprises a lower head and an upper head, the lower head is connected with the reflux section, the upper head is connected with the moderator output pipe, the upper head and the lower head are in a variable cross section structure, and the upper head protrudes towards the inflow section; the coolant circulation pipeline comprises an input cladding layer, an output cladding layer and a coolant cavity, the coolant cavity covers the cold pack cavity, the reflux section and part of the inflow section, so that a space between the cold pack cavity and the inflow section is in the coolant cavity, the input cladding layer surrounds a part of the moderator input pipe which is outside the coolant cavity, and the output cladding layer surrounds a part of the moderator output pipe which is outside the coolant cavity. The shape of the maximum cross section of the cold pack cavity is a sector of a circle arranged around the inflow section. The coolant circulation pipeline further comprises a coolant cavity sleeve, the coolant cavity sleeve is in communication with the input cladding layer and extends to the bottom of the coolant cavity, an end of the coolant cavity sleeve at the bottom of the coolant cavity is provided with a sleeve opening, and the sleeve opening is an inlet of the coolant in the coolant cavity. The input cladding layer and the inflow section are in a concentric circle structure, and the output cladding layer and the moderator output pipe are in a concentric circle structure.

2. The cold pack with enhanced heat dissipation capacity according to claim 1, wherein, The cold pack adopts the heat dissipation enhanced cold pack according to any one of claims 1 to 5.

3. The cold pack with enhanced heat dissipation capacity according to claim 1 or 2, characterized in that, Liquid hydrogen or deuterium is used as the moderator, and low-temperature helium is used as the coolant.

4. The heat dissipating enhanced cold pack of claim 3, wherein, The reactor-based cold neutron source adopts the reactor-based cold neutron source according to claim 6 or 7.

5. The cold pack with enhanced heat dissipation capacity according to claim 1 or 2, characterized in that, ​ 6. A pile-based cold neutron source comprising a cold package, characterized in that, ​ 7. The pile-based cold neutron source of claim 6, wherein, ​ 8. A reactor comprising a reactor-based cold neutron source, characterized in that, ​