CN101625907A - Shielding cover for preventing radiation of spent fuel - Google Patents
Shielding cover for preventing radiation of spent fuel Download PDFInfo
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- CN101625907A CN101625907A CN200910108972A CN200910108972A CN101625907A CN 101625907 A CN101625907 A CN 101625907A CN 200910108972 A CN200910108972 A CN 200910108972A CN 200910108972 A CN200910108972 A CN 200910108972A CN 101625907 A CN101625907 A CN 101625907A
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- spent fuel
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- inner cap
- enclosing cover
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Abstract
The invention discloses a shielding cover for preventing radiation of spent fuel, which is used for preventing radiation when a cover board of a spent fuel transport container is in the installation process. The shielding cover comprises an outer cover and an inner cover fixedly connected together and a neutron ray shielding board positioned between the outer cover and the inner cover. Because the invention adopts the outer cover and the inner cover fixedly connected together, and the outer cover and the inner cover are made of stainless steel materials, the invention can effectively shield gamma rays radiated by spent fuel components in the spent fuel transport container. The neutron ray shielding board is arranged between the outer cover and the inner cover, thereby neutron rays radiated by the spent fuel components in the spent fuel transport container can be effectively shielded.
Description
Technical field
The present invention relates to spentnuclear fuel (Spent Fuel; Irradiated Fuel) shield assembly technical field, more particularly, relate to a kind of in the process that the spent fuel transport container cover plate is installed the employed screening cover that prevents radiation of spent fuel.
Background technology
Spentnuclear fuel claims rradiated nuclear fuel again, is meant spent nuclear fuel in reactor.Nuclear fuel through neutron bombardment generation nuclear reaction, draws off in piling through certain hour in heap.But spentnuclear fuel contains a large amount of unspent fertile material 238U or 232Th, transuranic elements such as the neptunium that burn down and newly-generated easy fissioner 239Pu, 235U or 233U and nuclear fuel produce in the irradiation process, americium, curium also have fission element 90Sr, 137Cs, 99Tc etc. in addition.The spentnuclear fuel that draws off in pile must be transported to spentnuclear fuel reprocessing plant with spent fuel transport container after supercooling.
The spent fuel transport container that nuclear power station uses has two cover plates, i.e. inner cover plate and outer cover plate, and inner cover plate has 42 M38 bolts.Fill the spent fuel transport container of irradiated fuel assembly the above-mentioned bolt of inner cover plate is installed in fuel factory building service sink, its radioactive dosage comes from the structured material γ dosage of irradiated fuel assembly, being 900mrem/h (9mSv/h) during the container water-filling, is 2300mrem/h (23mSv/h) after the draining.When the inner cover plate bolt is installed, the close container work of operating personnel's palpus, and must divide three moment values in accordance with regulations tighten all bolts, the working time is longer, is easy to suffer the injury of radiation.Therefore, the radiation dose when how to reduce operating personnel inner cap being installed reduces the external exposure risk, is exactly the have to technical matters facing and solve of insider.
Summary of the invention
Embodiment of the invention technical matters to be solved is to provide a kind of screening cover that prevents radiation of spent fuel, its radiation dose when effectively the masking operation personnel install cover plate.
For solving the problems of the technologies described above, technical scheme of the present invention is: a kind of screening cover that prevents radiation of spent fuel is provided, be used for preventing the radiation of spent fuel transport container cover plate installation process, described screening cover comprises enclosing cover and the inner cap that is fixed together, and at least one neutron ray barricade between described enclosing cover and inner cap.
More specifically, form a cavity between described enclosing cover and the inner cap, described neutron ray barricade is located in the described cavity.
More specifically, described neutron ray barricade is the lead-boron polythene plate.
More specifically, in described cavity, also be provided with at least one stainless steel location-plate that is superimposed on the described neutron ray barricade.
More specifically, described enclosing cover and inner cap are made by stainless steel material.
More specifically, all relative side with inner cap of described enclosing cover is equipped with groove, and the cell wall of described enclosing cover groove extends an annular projection that can coincide with described inner cap groove inwall.
More specifically, described enclosing cover and inner cap both sides correspondence position are equipped with breach.
More specifically, the described screening cover that prevents radiation of spent fuel also comprises the sealing-plug that can coincide with described breach, and described sealing-plug is provided with handle.
More specifically, the upper surface of described enclosing cover is provided with at least one hanger.
Like this, because the present invention adopts enclosing cover and the inner cap that is fixed together, described enclosing cover and inner cap are made by stainless steel material, can effectively shield the gamma-rays of irradiated fuel assembly radiation in the spent fuel transport container; Between described enclosing cover and inner cap, be provided with the neutron ray barricade, thereby can effectively shield the neutron ray of irradiated fuel assembly radiation in the spent fuel transport container.
Description of drawings
Fig. 1 is the cross-sectional schematic of a preferred embodiment of the present invention;
Fig. 2 is the STRUCTURE DECOMPOSITION synoptic diagram of Fig. 1;
Fig. 3 is a schematic top plan view embodiment illustrated in fig. 1.
Embodiment
In order to make technical matters to be solved by this invention, technical scheme and beneficial effect clearer,, the present invention is further elaborated below in conjunction with drawings and Examples.Should be appreciated that specific embodiment described herein only in order to explanation the present invention, and be not used in qualification the present invention.
Please refer to Fig. 1 and Fig. 2, be a preferred embodiment of the present invention, this prevents that the screening cover of radiation of spent fuel is used for preventing the radiation of spent fuel transport container cover plate installation process, described screening cover comprises enclosing cover 1 and the inner cap 2 that is fixed together, and at least one neutron ray barricade 3 between described enclosing cover 1 and inner cap 2.Like this, because the present invention adopts enclosing cover 1 and the inner cap 2 be fixed together, described enclosing cover 1 and inner cap 2 are made by stainless steel material, can effectively shield the gamma-rays of irradiated fuel assembly radiation in the spent fuel transport container; Between described enclosing cover 1 and inner cap 2, be provided with neutron ray barricade 3, thereby can effectively shield the neutron ray of irradiated fuel assembly radiation in the spent fuel transport container.
Below above-mentioned each ingredient is described in detail respectively.
Described enclosing cover 1 and inner cap 2 can be made by stainless steel material, and both outside surfaces are all done polishing, so that clean decontamination in the future.In addition, stainless steel material can shield the gamma-rays of irradiated fuel assembly radiation in the spent fuel transport container.The all relative side with inner cap 2 of described enclosing cover 1 is equipped with groove, to form a cavity between described enclosing cover 1 and inner cap 2, comes ccontaining neutron ray barricade 3 and the stainless steel location-plate 4 that is used for fixing neutron ray barricade 3.In order to realize combining closely of enclosing cover 1 and inner cap 2, the cell wall of described enclosing cover 1 groove extends an annular projection 11 that can coincide with described inner cap 2 groove inwalls.Certainly, described annular projection 11 also can be located on the described inner cap 2.Described enclosing cover 1 welds together with the part that inner cap 2 contacts.Please refer to Fig. 3, owing to being covered with inflation and drainage flange in the spent fuel transport container, described enclosing cover 1 and inner cap 2 both sides correspondence positions are equipped with breach 12,21. Breach 12,21 places are provided with the sealing-plug (not shown), and described sealing-plug is provided with handle.When not needing to carry out flange mounting or dismounting operation,, reduce the personal radiation dose during the inner cap fitting operation with sealing- plug breach 12,21 beyond the Great Wall as far as possible.When needs carry out flange mounting or dismounting operation, remove sealing-plug by handle and get final product.The physical dimension of enclosing cover 1 and inner cap 2 can be set according to covering bolt position in the spent fuel transport container, and with fixing of cap bolt in not influencing, the mounting or dismounting that do not influence inflation and drainage flange are operating as principle.In addition, because the screening cover that prevents radiation of spent fuel is comparatively heavy, is convenient carrying and installs that the upper surface of described enclosing cover 1 is provided with four hangers 13, certainly the quantity of hanger 13 can also for one or two etc.
Described neutron ray barricade 3 is the lead-boron polythene plate, with the neutron ray function of shielding that utilizes the lead-boron polythene material to be had.Certainly, neutron ray barricade 3 can also adopt other materials with similar or similar functions to make.The thickness of neutron ray barricade 3 (being the lead-boron polythene plate) can be about 10mm.
Daya Bay nuclear power plant reduces to screening cover outside surface exposure dose and is no more than 2mSv/h owing to adopted the screening cover that prevents radiation of spent fuel of present embodiment, and the radiation protection effect is very desirable, provides one to ensure reliably to health of operators.
Should be pointed out that present embodiment not only can be applicable to cover in the spent fuel transport container installation of bolt, also has use value for other similar applications.
The above only is preferred embodiment of the present invention, not in order to restriction the present invention, all any modifications of being done within the spirit and principles in the present invention, is equal to and replaces and improvement etc., all should be included within protection scope of the present invention.
Claims (9)
1, a kind of screening cover that prevents radiation of spent fuel, be used for preventing the radiation of spent fuel transport container cover plate installation process, it is characterized in that: described screening cover comprises enclosing cover and the inner cap that is fixed together, and at least one neutron ray barricade between described enclosing cover and inner cap.
2, the screening cover that prevents radiation of spent fuel as claimed in claim 1 is characterized in that: form a cavity between described enclosing cover and the inner cap, described neutron ray barricade is located in the described cavity.
3, the screening cover that prevents radiation of spent fuel as claimed in claim 1 is characterized in that: described neutron ray barricade is the lead-boron polythene plate.
4, the screening cover that prevents radiation of spent fuel as claimed in claim 2 is characterized in that: also be provided with at least one stainless steel location-plate that is superimposed on the described neutron ray barricade in described cavity.
5, the screening cover that prevents radiation of spent fuel as claimed in claim 1, it is characterized in that: described enclosing cover and inner cap are made by stainless steel material.
6, the screening cover that prevents radiation of spent fuel as claimed in claim 5 is characterized in that: all relative side with inner cap of described enclosing cover is equipped with groove, and the cell wall of described enclosing cover groove extends an annular projection that can coincide with described inner cap groove inwall.
7, the screening cover that prevents radiation of spent fuel as claimed in claim 1 is characterized in that: inflation and drainage flange position on the corresponding described spent fuel transport container cover plate of described enclosing cover and inner cap are provided with breach.
8, the screening cover that prevents radiation of spent fuel as claimed in claim 7 is characterized in that: the described screening cover that prevents radiation of spent fuel also comprises the sealing-plug that can coincide with described breach, and described sealing-plug is provided with handle.
9, the screening cover that prevents radiation of spent fuel as claimed in claim 1, it is characterized in that: the upper surface of described enclosing cover is provided with at least one hanger.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910108972A CN101625907A (en) | 2009-07-22 | 2009-07-22 | Shielding cover for preventing radiation of spent fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN200910108972A CN101625907A (en) | 2009-07-22 | 2009-07-22 | Shielding cover for preventing radiation of spent fuel |
Publications (1)
| Publication Number | Publication Date |
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| CN101625907A true CN101625907A (en) | 2010-01-13 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN200910108972A Pending CN101625907A (en) | 2009-07-22 | 2009-07-22 | Shielding cover for preventing radiation of spent fuel |
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| CN (1) | CN101625907A (en) |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103106938A (en) * | 2013-01-28 | 2013-05-15 | 华北电力大学 | Spent fuel shipping container with shock absorption and striking resistant spring device |
| CN104575648A (en) * | 2014-12-24 | 2015-04-29 | 中国原子能科学研究院 | Conveying container for fast reactor MOX fuel component |
| CN107180661A (en) * | 2017-03-30 | 2017-09-19 | 中国核动力研究设计院 | A kind of spent fuel transport container residual heat removal facility |
| CN107767980A (en) * | 2016-08-19 | 2018-03-06 | 中国辐射防护研究院 | A kind of long-range Water pipeline radiation focus screening arrangement |
| CN108317395A (en) * | 2017-12-20 | 2018-07-24 | 中核四0四有限公司 | A kind of grass-hopper of feed liquid containing neptunium |
| CN108417284A (en) * | 2018-02-13 | 2018-08-17 | 中国核电工程有限公司 | A kind of nuclear fuel reprocessing plant's plutonium product transfer device |
| CN110444306A (en) * | 2018-10-25 | 2019-11-12 | 清华大学天津高端装备研究院 | A kind of spent fuel transport container |
| CN111561576A (en) * | 2020-05-14 | 2020-08-21 | 北京利方达真空技术有限责任公司 | Vacuum gate valve with neutron shielding function |
| CN111933323A (en) * | 2020-07-22 | 2020-11-13 | 上海核工程研究设计院有限公司 | Radiation protection structure of spent fuel transport ship |
| CN113223742A (en) * | 2021-04-19 | 2021-08-06 | 中广核工程有限公司 | Radiation shielding and insulating device |
-
2009
- 2009-07-22 CN CN200910108972A patent/CN101625907A/en active Pending
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103106938A (en) * | 2013-01-28 | 2013-05-15 | 华北电力大学 | Spent fuel shipping container with shock absorption and striking resistant spring device |
| CN103106938B (en) * | 2013-01-28 | 2015-10-21 | 华北电力大学 | A kind of spent fuel transport container with damping, protecting against shock spring assembly |
| CN104575648A (en) * | 2014-12-24 | 2015-04-29 | 中国原子能科学研究院 | Conveying container for fast reactor MOX fuel component |
| CN104575648B (en) * | 2014-12-24 | 2017-05-03 | 中国原子能科学研究院 | Conveying container for fast reactor MOX fuel component |
| CN107767980A (en) * | 2016-08-19 | 2018-03-06 | 中国辐射防护研究院 | A kind of long-range Water pipeline radiation focus screening arrangement |
| CN107180661A (en) * | 2017-03-30 | 2017-09-19 | 中国核动力研究设计院 | A kind of spent fuel transport container residual heat removal facility |
| CN108317395A (en) * | 2017-12-20 | 2018-07-24 | 中核四0四有限公司 | A kind of grass-hopper of feed liquid containing neptunium |
| CN108417284A (en) * | 2018-02-13 | 2018-08-17 | 中国核电工程有限公司 | A kind of nuclear fuel reprocessing plant's plutonium product transfer device |
| CN110444306A (en) * | 2018-10-25 | 2019-11-12 | 清华大学天津高端装备研究院 | A kind of spent fuel transport container |
| CN111561576A (en) * | 2020-05-14 | 2020-08-21 | 北京利方达真空技术有限责任公司 | Vacuum gate valve with neutron shielding function |
| CN111933323A (en) * | 2020-07-22 | 2020-11-13 | 上海核工程研究设计院有限公司 | Radiation protection structure of spent fuel transport ship |
| CN113223742A (en) * | 2021-04-19 | 2021-08-06 | 中广核工程有限公司 | Radiation shielding and insulating device |
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Application publication date: 20100113 |