CN101335061B - Fuel Damage Delayed Neutron Detection Device - Google Patents
Fuel Damage Delayed Neutron Detection Device Download PDFInfo
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- CN101335061B CN101335061B CN2008101352337A CN200810135233A CN101335061B CN 101335061 B CN101335061 B CN 101335061B CN 2008101352337 A CN2008101352337 A CN 2008101352337A CN 200810135233 A CN200810135233 A CN 200810135233A CN 101335061 B CN101335061 B CN 101335061B
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- neutron
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- delayed
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- 230000003111 delayed effect Effects 0.000 title claims abstract description 29
- 239000000446 fuel Substances 0.000 title claims abstract description 27
- 238000001514 detection method Methods 0.000 title abstract description 12
- 238000010521 absorption reaction Methods 0.000 claims abstract description 19
- 230000015556 catabolic process Effects 0.000 claims description 13
- 238000006731 degradation reaction Methods 0.000 claims description 13
- 229910052793 cadmium Inorganic materials 0.000 claims description 7
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 claims description 7
- 239000004698 Polyethylene Substances 0.000 claims description 6
- 239000000463 material Substances 0.000 claims description 6
- -1 polyethylene Polymers 0.000 claims description 6
- 229920000573 polyethylene Polymers 0.000 claims description 6
- 238000006243 chemical reaction Methods 0.000 claims description 4
- 230000005251 gamma ray Effects 0.000 claims description 4
- JEIPFZHSYJVQDO-UHFFFAOYSA-N iron(III) oxide Inorganic materials O=[Fe]O[Fe]=O JEIPFZHSYJVQDO-UHFFFAOYSA-N 0.000 claims description 2
- 239000003973 paint Substances 0.000 claims description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract description 6
- 229910052708 sodium Inorganic materials 0.000 abstract description 6
- 239000011734 sodium Substances 0.000 abstract description 6
- 230000000903 blocking effect Effects 0.000 abstract 1
- 238000000034 method Methods 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 3
- 229910052796 boron Inorganic materials 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 229910000975 Carbon steel Inorganic materials 0.000 description 2
- 239000010962 carbon steel Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 2
- HGAZMNJKRQFZKS-UHFFFAOYSA-N chloroethene;ethenyl acetate Chemical compound ClC=C.CC(=O)OC=C HGAZMNJKRQFZKS-UHFFFAOYSA-N 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 241000357293 Leptobrama muelleri Species 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000003550 marker Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a delayed neutron detection device for detecting fuel element damage. The device comprises a detection station, a detector, an amplifier, a shaper, a processor, a display and alarm terminal and the like, wherein all the parts are connected through cables. The neutron detector and the detector guide pipe are arranged in the middle of the rectangular shell, a moderation layer for delayed neutrons is arranged around the detector guide pipe, and a plate-shaped lead shield for blocking gamma rays is arranged on the inner side of the detector guide pipe. In order to reduce the interference of background neutrons, except for the inner side facing the reactor core, plate-shaped slowing layers and absorption layers aiming at the background neutrons are arranged on the upper side, the lower side, the front side, the rear side and the outer side of the rectangular shell. The lead shielding layer, the slowing layer and the absorbing layer are all in a plate shape, can be stacked to change the thickness, are convenient to plug and pull, and are convenient to install, disassemble and replace. And simultaneously, the safety risk caused by leading out sodium is avoided.
Description
Technical field
The invention belongs to the neutron detection technical field, be specifically related to a kind of delayed neutron sniffer that fuel element failure is used of surveying.
Background technology
No matter presurized water reactor still is a fast neutron increment heap, and the detection of fuel element failure all is a problem that receives much concern.Usually; What the presurized water reactor fuel element rupture detection used is to sob the suction detection method; Promptly detect the tightness of fuel assembly, its principle is through isolating fuel assembly to be detected, improving the interior pressure (heating) of fuel or the external pressure of reduction fuel; Accelerate fission product and outwards discharge, whether exist to survey fission product through the involucrum of burst slug.In addition, Chinese patent 200610087597.3 discloses another kind of burst slug position detection method, promptly monitors the gamma dose variation tendency between dump chest in real time, judges whether to meet characteristic curve, meets characteristic curve, shows that then breakage has taken place burst slug.Chinese patent 85105572 also discloses a kind of method of discerning damaged reactor components; This method is to be put into reactor components inside to solid mark material; Particularly fuel element is inner; Under the irradiation of neutron, that marker material can produce is stable, detectable, can discern and measurable isotope gas.These fuel element failure detection method operation more complicated, required equipment is more.
Whether whether damaged method has been used in the presurized water reactor to utilize delayed neutron to survey fuel element, and this method is that the water in a loop is drawn, damaged with detecting element through the total γ that surveys fission product in the water.But this method can not be used for sodium-cooled fast reactor, because the risk that the sodium in a loop is drawn is very big.
Summary of the invention
(1) goal of the invention
The present invention is directed to the deficiency of prior art, a kind of sniffer of fuel element failure of fairly simple practicality is provided.
(2) technical scheme
For realizing above-mentioned purpose, the present invention provides following technical scheme.
A kind of fuel degradation delayed neutron sniffer comprises several parts such as acquisition station, detector, amplifier and former, processor, demonstration and alarm terminal, connects through cable between the each several part.Key is that acquisition station is a rectangle, in the middle of the rectangle shell, places neutron detector and detector conduit, is provided with the slowing down layer to delayed neutron around the detector conduit, and the acquisition station inboard is provided with and stops gamma-ray tabular lead shield.In order to subdue the interference of background neutron, except the inboard of orientating reaction heap reactor core, upper and lower, the forward and backward and outside of rectangle shell all be provided with tabular slowing down layer and absorption layer to background neutron.
In order to increase the reliability of sniffer, 2 neutron detectors are installed in each acquisition station.
In addition, intact reliable for assurance device, be provided with check neutron source conduit at the neutron detector conduit fitting, in case of necessity neutron source is hung in from the neutron source conduit, whether the check sniffer is in proper working order.
(3) invention effect
The present invention piles the relative fluence rate of the delayed neutron that discharges in the circuit cools agent sodium through detection reaction, judges the exposed damaged order of severity of fuel, to guarantee reactor safety.Lead shield, slowing down layer and absorption layer in the device all adopts tabular, can stack change thickness, and plug is convenient, is convenient to install and change.Avoided simultaneously therefore sodium drawn the security risk brought.
Description of drawings
Fig. 1 fuel degradation delayed neutron sniffer structural representation;
The cut-away view at A-A place among Fig. 2 Fig. 1.
Among the figure, 1a, inboard lead shield layer; 1b, inboard lead shield layer; 1c, inboard lead shield layer; 1d, inboard lead shield layer; 2, BF
3Proportional counter tube; 3, neutron detector conduit; 4, amplifier and former; 5, processor; 6, demonstration and alarm terminal; 7, neutron source conduit; 8, detector top cover; 9, top lead shield layer; 10, shielding slowing down layer; 11, boron-containing shield absorption layer; 12, cadmium shield absorption layer; 13, outside lead shield layer; 14, delayed neutron slowing down layer; 15, bottom lead shield layer; 16, inner support panels; 17, shell.
Embodiment
Below in conjunction with accompanying drawing technical scheme of the present invention is done further to set forth.
As shown in Figure 1, a kind of sniffer that is used for the sodium-cooled fast reactor fuel element rupture detection is piled the relative fluence rate of delayed neutron in the circuit cools agent sodium through detection reaction, judges the exposed damaged order of severity of fuel element, to guarantee reactor safety.The delayed neutron sniffer is installed in the outside of the heap container relative with main heat exchanger, surveys by the delayed neutron that discharges in the main heat exchanger, i.e. the delayed neutron that discharges of a loop sodium.。
This device comprises several parts such as acquisition station, detector, amplifier and former 4, processor 5, demonstration and alarm terminal 6, connects through cable between the each several part.For guaranteeing that in the state of accident this acquisition station can not cave in and lose efficacy by the too high tygon that causes of Yin Wendu, this acquisition station outside is firm rectangle carbon steel shell 17, and shell 17 tops are provided with top cover 8, are coated with rust protection paint outward, and medial surface is to main heat exchanger.The inboard of shell 17 is provided with the gamma-ray tabular lead shield layer that stops from reactor core, and present embodiment uses 4, is respectively inboard lead shield layer 1a, 1b, 1c, 1d, and its material is Pb-2, and gross thickness is 50～150mm.Neutron detector conduit 3, built-in neutron counter tube 2 are installed in the shell middle part.Neutron counter tube 2 can be BF
3Proportional counter tube can be other neutron detectors also, because of BF
3Proportional counter tube has higher anti-γ ability, and present embodiment adopts BF
3Proportional counter tube.For satisfying redundancy, counter tube conduit 3 can be provided with 1～2, and a BF is respectively placed in 2 of present embodiment designs in it
3Proportional counter tube 2.As shown in Figure 2, near the detector conduit, establish check neutron source conduit 7, in case of necessity neutron source is hung in from neutron source conduit 7, whether the check sniffer is in proper working order.For the delayed neutron of slowing down, establish around detector conduit and the neutron source conduit and be surrounded by the thick high pressure polyethylene delayed neutron slowing down layer 14 of 25～50mm from reactor core one side.In order to subdue the interference of background neutron,, set gradually tabular shielding slowing down layer 10, tabular shielding absorption layer 11,12, tabular lead shield layer 13 at forward and backward, the lateral surface of shell.The tabular shielding absorption layer of present embodiment is two-layer, and one deck is to adopt the thick cadmium plate 12 of 8～15mm to absorb thermal neutron, and another layer is to absorb epithermal neutron with the thick boracic polyethylene board 11 of 20～40mm.The tygon that shields tabular absorption layer 11 usefulness boracics (B) remedies the incomplete absorption of cadmium to epithermal neutron; Because cadmium only has higher absorption cross section to thermal neutron; The absorption cross section of neutron energy cadmium during greater than 0.5ev is obviously not as boron, and the absorption cross section of neutron energy cadmium when 1.5ev has only 1/10 of boron.Tabular slowing down layer 10 adopts 60～100mm thick polyethylene material, and present embodiment adopts the 80mm thick polyethylene.Equally, according to tabular lead shield layer, tabular absorption layer, tabular slowing down layer all are set, its difference is that above shell 17, neutron detector conduit 3 passes top lead shield 9 with neutron source conduit 7 at the upper and lower of shell 17.Below shell 17,, between bottom lead shield and following shielding absorption layer 15, carbon steel back up pad 16 is set for increasing detector bottom support intensity.
Temperature is higher in the reactor pit, and detector is operated in the high-temperature region in the reactor pit, and working temperature is 80 ℃.Amplifier and former 4 are installed in the upper shielding layer of reactor, and working temperature is at 50 ℃.Processor 5, demonstration and alarm terminal 6 etc. are installed in the pulpit.
Obviously, those skilled in the art can carry out various changes and modification to the present invention and not break away from the spirit and scope of the present invention.Like this, belong within the scope of claim of the present invention and equivalent technologies thereof if of the present invention these are revised with modification, then the present invention also is intended to comprise these changes and modification interior.
Claims (10)
1. fuel degradation delayed neutron sniffer; Comprise acquisition station, detector, amplifier and former (4), processor (5), demonstration and alarm terminal (6); Connect through cable between the each several part, it is characterized in that: acquisition station is outside to be rectangular parallelepiped shell (17), in the middle of shell (17), places neutron detector (2) and neutron detector conduit (3); Be provided with the slowing down layer (14) to delayed neutron around detector conduit (3), the inboard is provided with and stops gamma-ray tabular lead shield; Except the inboard of orientating reaction heap reactor core, all be provided with tabular slowing down layer and absorption layer to background neutron in upper and lower, the forward and backward and outside of rectangular parallelepiped shell (17).
2. fuel degradation delayed neutron sniffer according to claim 1 is characterized in that: described shell (17) top is provided with top cover (8); Be coated with rust protection paint outward; Medial surface is to main heat exchanger.
3. fuel degradation delayed neutron sniffer according to claim 1 is characterized in that: described neutron detector conduit (3) is 1～2.
4. according to claim 1 or 3 described fuel degradation delayed neutron sniffers, it is characterized in that: establish check neutron source conduit (7) near the described neutron detector conduit (3).
5. fuel degradation delayed neutron sniffer according to claim 1 is characterized in that: described neutron detector (2) is BF
3Proportional counter tube.
6. fuel degradation delayed neutron sniffer according to claim 1 is characterized in that: described slowing down layer (14) to delayed neutron is the thick high pressure polyethylene material of 25～50mm.
7. fuel degradation delayed neutron sniffer according to claim 1; It is characterized in that: described inboard is provided with and stops that gamma-ray tabular lead shield is 4; Ecto-entad is the first inboard lead shield layer (1a), the second inboard lead shield layer (1b), the 3rd inboard lead shield layer (1c) and the 4th inboard lead shield layer (1d) successively; Material is Pb-2, and 4 tabular lead shield layer gross thickness are 50～150mm.
8. fuel degradation delayed neutron sniffer according to claim 1 is characterized in that: forward and backward, the lateral surface of described rectangular parallelepiped shell (17) sets gradually tabular shielding slowing down layer (10), the first tabular shielding absorption layer (11), the second tabular shielding absorption layer (12) and tabular lead shield layer (13).
9. fuel degradation delayed neutron sniffer according to claim 8 is characterized in that: the described first tabular shielding absorption layer (11) is the thick cadmium plate of 8～15mm, and the second tabular shielding absorption layer (12) is the thick boracic polyethylene board of 20～40mm.
10. fuel degradation delayed neutron sniffer according to claim 1; It is characterized in that: described detector is arranged on the high-temperature region in the reactor pit; Amplifier and former (4) are installed in the upper shielding layer of reactor, and processor (5), demonstration and alarm terminal (6) are installed in the pulpit.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2008101352337A CN101335061B (en) | 2008-08-06 | 2008-08-06 | Fuel Damage Delayed Neutron Detection Device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2008101352337A CN101335061B (en) | 2008-08-06 | 2008-08-06 | Fuel Damage Delayed Neutron Detection Device |
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| Publication Number | Publication Date |
|---|---|
| CN101335061A CN101335061A (en) | 2008-12-31 |
| CN101335061B true CN101335061B (en) | 2012-02-15 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2008101352337A Active CN101335061B (en) | 2008-08-06 | 2008-08-06 | Fuel Damage Delayed Neutron Detection Device |
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Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103424767B (en) * | 2012-05-22 | 2016-03-30 | 中国原子能科学研究院 | In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content |
| CN105334234A (en) * | 2015-11-27 | 2016-02-17 | 天津普达软件技术有限公司 | Shielding mechanism suitable for multi-purpose scanning of gamma scanner |
| CN110467865B (en) * | 2018-05-09 | 2021-12-28 | 同方威视技术股份有限公司 | Boron coating method |
| CN112130193A (en) * | 2020-08-20 | 2020-12-25 | 中国原子能科学研究院 | Moderating body device |
| CN112908498B (en) * | 2021-03-30 | 2022-03-29 | 陕西卫峰核电子有限公司 | Irradiation-resistant slowing shielding device and assembling method thereof |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4415524A (en) * | 1981-04-28 | 1983-11-15 | The United States Of America As Represented By The United States Department Of Energy | Apparatus for and method of monitoring for breached fuel elements |
| EP0258958A1 (en) * | 1986-08-18 | 1988-03-09 | Westinghouse Electric Corporation | Locating a breached fuel assembly in a nuclear reactor on-line |
| CN201242880Y (en) * | 2008-08-06 | 2009-05-20 | 中国原子能科学研究院 | Device for detecting fuel breakage delayed neutron |
-
2008
- 2008-08-06 CN CN2008101352337A patent/CN101335061B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4415524A (en) * | 1981-04-28 | 1983-11-15 | The United States Of America As Represented By The United States Department Of Energy | Apparatus for and method of monitoring for breached fuel elements |
| EP0258958A1 (en) * | 1986-08-18 | 1988-03-09 | Westinghouse Electric Corporation | Locating a breached fuel assembly in a nuclear reactor on-line |
| CN201242880Y (en) * | 2008-08-06 | 2009-05-20 | 中国原子能科学研究院 | Device for detecting fuel breakage delayed neutron |
Non-Patent Citations (1)
| Title |
|---|
| 刘玉璞，刘浩杰.压水堆核燃料破损探测系统研制.《全国第四届核反应堆用核仪器学术会议论文集》.2005,20-23. * |
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| CN101335061A (en) | 2008-12-31 |
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Inventor after: Liu Yupu Inventor after: Xu Mi Inventor after: Liu Haojie Inventor after: Jiang Tingsan Inventor after: Li Weifang Inventor before: Liu Yupu Inventor before: Liu Haojie Inventor before: Jiang Tingsan Inventor before: Li Weifang |
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Free format text: CORRECT: INVENTOR; FROM: LIU YUPU LIU HAOJIE JIANG TINGSAN LI WEIFANG TO: LIU YUPU XU XU LIU HAOJIEJIANG TINGSAN LI WEIFANG |
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