JP4815100B2 - Transport and storage containers for radioactive materials that generate heat, especially spent nuclear fuel elements or high-level radioactive waste-glass solids - Google Patents
Transport and storage containers for radioactive materials that generate heat, especially spent nuclear fuel elements or high-level radioactive waste-glass solids Download PDFInfo
- Publication number
- JP4815100B2 JP4815100B2 JP2003411999A JP2003411999A JP4815100B2 JP 4815100 B2 JP4815100 B2 JP 4815100B2 JP 2003411999 A JP2003411999 A JP 2003411999A JP 2003411999 A JP2003411999 A JP 2003411999A JP 4815100 B2 JP4815100 B2 JP 4815100B2
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- Prior art keywords
- transport
- cylinder
- storage container
- container
- container body
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- 239000012857 radioactive material Substances 0.000 title claims abstract description 8
- 230000002285 radioactive effect Effects 0.000 title claims description 4
- 239000011521 glass Substances 0.000 title description 2
- 239000007787 solid Substances 0.000 title description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 title description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 13
- 229910002804 graphite Inorganic materials 0.000 claims abstract description 13
- 239000010439 graphite Substances 0.000 claims abstract description 13
- 239000000463 material Substances 0.000 claims abstract description 8
- 239000002184 metal Substances 0.000 claims description 11
- 229910052751 metal Inorganic materials 0.000 claims description 11
- 239000011248 coating agent Substances 0.000 claims description 6
- 238000000576 coating method Methods 0.000 claims description 6
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 claims description 3
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- 229910052802 copper Inorganic materials 0.000 claims description 3
- 239000010949 copper Substances 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- 230000002093 peripheral effect Effects 0.000 abstract description 2
- 239000002699 waste material Substances 0.000 abstract 1
- 238000000034 method Methods 0.000 description 3
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 2
- 229910052739 hydrogen Inorganic materials 0.000 description 2
- 239000001257 hydrogen Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Gasification And Melting Of Waste (AREA)
- Glass Compositions (AREA)
Abstract
Description
本発明は、閉鎖要素を備えた中性子減速材1を有する金属製の容器本体と、放射性物質用の収容筒体とこれらの収容筒体間に空筒体を備えている、容器本体内に設けられたバスケットとから成る、熱を発生する放射性物質、特に使用済み原子炉燃料要素または高レベル放射性廃棄物(high level waste)−ガラス固化体のための輸送兼貯蔵容器に関する。 The present invention is provided in a container body having a metal container body having a neutron moderator 1 having a closing element, a housing cylinder for radioactive material, and an empty cylinder between these housing cylinders. Heat transferable radioactive material, in particular spent nuclear fuel elements or high level waste-transport and storage containers for vitrified bodies.
従来様式の実際から一般的に公知の輸送兼貯蔵容器にあって、空筒体は小さすぎて通常は利用されないままである。中性子放出を遮蔽するために、高速中性子の熱中性子化が、容器本体内の水素を含有する材料かあるいは外部に位置する中性子減速材によって、あるいは−二番目の可能性として−水素を含有する、二次ガンマ線照射を用いてホウ素化された材料、例えば外部の容器壁に設けられた合成物質の形で行われる。この二次ガンマ線放射により、容器の外部、特に弱い場所での総ガンマ線量率が増加する。通常、中性子遮蔽の弱い場所は、容器の外部で付加的な遮蔽材料を用いて、例えば輸送木枠で緩和される。これには総じてかなりの費用がかかるが改善するに値するものである。 In transport and storage containers generally known from the practice of conventional modalities, the hollow cylinder is too small to be normally utilized. In order to shield neutron emission, thermal neutronization of fast neutrons can be either hydrogen-containing material in the vessel body or by externally located neutron moderators, or, as a second possibility, containing hydrogen. It is carried out in the form of a material boronated using secondary gamma irradiation, for example a synthetic substance provided on the outer container wall. This secondary gamma radiation increases the total gamma dose rate outside the container, especially in weak areas. Typically, areas with weak neutron shielding are mitigated with an additional shielding material outside the vessel, for example with a transport crate. This generally costs quite a bit but is worth improving.
本発明の基礎となる課題は、中性子線量率の全体レベルの必要な低減が従来以上に単純な様式と方法で達成されるように、冒頭で挙げられた様式の輸送兼貯蔵容器を形成することである。 The problem underlying the present invention is to form a transport and storage vessel of the type mentioned at the beginning so that the necessary reduction of the overall level of the neutron dose rate is achieved in a simpler manner and method than before. It is.
このような課題の本発明による解決策は、少なくとも周辺の空筒体がグラファイトを含有する中性子減速材で充填されていることである。 The solution according to the present invention for such a problem is that at least the peripheral hollow body is filled with a neutron moderator containing graphite.
本発明は、グラファイトが特殊な中性子減速材であるだけではなく、グラファイトの高い熱伝導率と放射係数が熱除去に極めて有利な作用を及ぼすという認識から出発している。従って記載された処置により放射性物質の温度が著しく下がることが達せられる。 The present invention starts from the recognition that not only graphite is a special neutron moderator, but also the high thermal conductivity and radiation coefficient of graphite have a very advantageous effect on heat removal. Thus, the described procedure achieves a significant decrease in the temperature of the radioactive material.
他の実施形態に関して、本発明の範囲においては多くの可能性がある。好ましい実施の形態によれば、周辺の空筒体はくさび形状に形成されている。特に中性子減速材は加圧したグラファイトから成る。中性子減速材は有利に柱状に形成されている。空間部にある中性子減速材の少なくとも一部は適切な方法で金属被覆部を備えている。これらは熱伝導を改善するために容器本体とネジで固定されているか或いは容器本体壁部にネジで固定された案内条片を介して容器本体と緊張状態で固定されている。さらに同じ理由から、金属被覆部は銅材あるいは鋼材で製造されるのが望ましい。さらにその他の点では、頭部側および/または脚部側の容器中空空域はグラファイトで覆うことが望ましい。 With respect to other embodiments, there are many possibilities within the scope of the present invention. According to a preferred embodiment, the superficial body around are formed in a wedge shape. In particular, the neutron moderator is made of pressurized graphite. The neutron moderator is preferably columnar. At least a portion of the neutron moderator in the space is provided with a metal coating in an appropriate manner. In order to improve heat conduction, these are fixed to the container main body with screws, or are fixed to the container main body in a tension state via guide strips fixed to the container main body wall with screws. Furthermore, for the same reason, it is desirable that the metal coating is made of copper or steel. In other respects, it is desirable that the container hollow air space on the head side and / or the leg side be covered with graphite.
本発明の構成により、中性子線量率の全体レベルの必要な低減が従来以上に簡単な様式と方法で達成される。 With the arrangement of the present invention, the necessary reduction of the overall level of neutron dose rate is achieved in a simpler manner and method than before.
以下に、本発明を実施の形態に基づいてより詳しく説明する。唯一の図面は輸送兼貯蔵容器の横断面を示す。 Hereinafter, the present invention will be described in more detail based on embodiments. The only drawing shows the cross section of the shipping and storage container.
図で示された輸送兼貯蔵容器は、熱を発生する放射性物質、特に使用済みの原子炉燃料要素または高レベル放射性廃棄物−ガラス固化体のための輸送兼貯蔵容器として規定されており、容器の根本的な構造において、詳細には示されていない閉鎖要素を備えた、中性子減速材1を有する金属製の容器本体2から成る。容器本体2内には、バスケット3が設けられており、このバスケットが放射性物質用の収容筒体4とこれらの収容筒体間に空筒体5とを備えている。
The transport and storage container shown in the figure is defined as a transport and storage container for radioactive materials that generate heat, in particular for used nuclear reactor fuel elements or high-level radioactive waste-glass solids. In the basic structure of FIG. 1, it consists of a
図から明らかなように、周辺の空筒体5はグラファイトを含む中性子減速材1で充填されている。周辺の空筒体5と、対応してその中にある中性子減速材1も、くさび形状に形成されている。本実施形態では、この中性子減速材1は加圧したグラファイト柱状物から成る。これらのグラファイト柱状物は、その周囲の一部分に渡って銅材あるいは鋼材から成る金属被覆部6を備えており、この金属被覆部は容器本体1とネジで固定されている。しかも、金属被覆部6は容器本体壁部にネジで固定された案内条片を介して、容器頭部と緊張状態で固定されている。 As is apparent from the figure, the surrounding hollow body 5 is filled with a neutron moderator 1 containing graphite. An empty cylinder 5 near neutron moderator 1 in it correspondingly also formed in a wedge shape. In the present embodiment, the neutron moderator 1 is made of a pressurized graphite column. These graphite pillars are provided with a metal coating 6 made of copper or steel over a part of the periphery thereof, and the metal coating is fixed to the container body 1 with screws. In addition, the metal cover 6 is fixed in tension with the container head via a guide strip fixed to the container body wall with a screw.
頭部側および/または脚部側の容器中空領域が同様にグラファイトで覆われていることは、詳細には示されていない。 It has not been shown in detail that the container hollow regions on the head side and / or on the leg side are likewise covered with graphite.
1 中性子減速材
2 容器本体
3 バスケット
4 収容筒体
5 空筒体
6 金属被覆部
DESCRIPTION OF SYMBOLS 1
Claims (8)
少なくとも周辺の、前記容器本体(2)の内側に沿って配置された前記空筒体(5)がグラファイトを含有する前記中性子減速材(1)で充填されていることと、
前記収容筒体(4)が円形断面を有して形成されており、および前記バスケット(3)が、前記収容筒体(4)の一つが前記容器本体(2)の中央に配置され、他の収容筒体(4)が中央に配置された収容筒体(4)の周囲にわたって放射状に配置されるよう形成されていることを特徴とする輸送兼貯蔵容器。 A metallic container body (2) having a neutron moderator (1) provided with a closing element, a radioactive cylinder housing cylinder (4), and an empty cylinder body (5) between these housing cylinders (4) In a transport and storage container for radioactive material generating heat, comprising a basket (3) provided in the container body (2) comprising:
The hollow cylinder (5) disposed along the inside of the container body (2) at least in the periphery is filled with the neutron moderator (1) containing graphite;
The accommodating cylinder (4) is formed with a circular cross section, and the basket (3) is arranged such that one of the accommodating cylinders (4) is arranged at the center of the container body (2), The transport and storage container is characterized in that the storage cylinder (4) is radially arranged over the periphery of the storage cylinder (4) disposed in the center.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
EP02028964.1 | 2002-12-24 | ||
EP02028964A EP1434239B1 (en) | 2002-12-24 | 2002-12-24 | Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells |
Publications (2)
Publication Number | Publication Date |
---|---|
JP2004205503A JP2004205503A (en) | 2004-07-22 |
JP4815100B2 true JP4815100B2 (en) | 2011-11-16 |
Family
ID=32405726
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2003411999A Expired - Lifetime JP4815100B2 (en) | 2002-12-24 | 2003-12-10 | Transport and storage containers for radioactive materials that generate heat, especially spent nuclear fuel elements or high-level radioactive waste-glass solids |
Country Status (4)
Country | Link |
---|---|
EP (1) | EP1434239B1 (en) |
JP (1) | JP4815100B2 (en) |
AT (1) | ATE385607T1 (en) |
DE (1) | DE50211653D1 (en) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE102004049236B4 (en) * | 2004-10-09 | 2006-07-13 | GNS Gesellschaft für Nuklear-Service mbH | Transport and/or storage container for nuclear fuel elements, comprises a carrier inside the container, and a number of receiving sections for the fuel elements |
DE102010003289B4 (en) * | 2010-03-25 | 2017-08-24 | Ald Vacuum Technologies Gmbh | Containers for the storage of radioactive waste and process for its production |
JP6143573B2 (en) * | 2013-06-20 | 2017-06-07 | 三菱重工業株式会社 | Radioactive substance storage basket and radioactive substance storage container |
RU2686476C1 (en) * | 2018-06-05 | 2019-04-29 | Александр Натанович Капилевич | Container cover for spent nuclear fuel transportation and storage |
US10878972B2 (en) | 2019-02-21 | 2020-12-29 | Deep Isolation, Inc. | Hazardous material repository systems and methods |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3012310A1 (en) * | 1980-03-29 | 1981-10-08 | Transnuklear Gmbh, 6450 Hanau | INSERT BASKET FOR RADIOACTIVE MATERIAL IN TRANSPORT AND / OR STORAGE CONTAINERS |
DE3012256A1 (en) * | 1980-03-29 | 1981-10-15 | Transnuklear Gmbh, 6450 Hanau | CONTAINER FOR TRANSPORT AND / OR STORAGE OF RADIOACTIVE SUBSTANCES |
DE3017985A1 (en) * | 1980-05-10 | 1981-11-12 | Vox lumatic GmbH, 7302 Ostfildern | Transport and storage vessel for radioactive materials - has shielding conductive material esp. graphite between thick outer wall and inner sealed containment |
DE3103557A1 (en) * | 1981-02-03 | 1982-12-09 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | "TRANSPORT AND STORAGE CONTAINERS FOR RADIOACTIVE WASTE" |
JPS59132396A (en) * | 1983-01-18 | 1984-07-30 | 株式会社神戸製鋼所 | Method of making storage container of radioactive material |
JPS61111494A (en) * | 1984-11-06 | 1986-05-29 | 三菱重工業株式会社 | Irradiation agent fuel storage facility |
US4827139A (en) * | 1987-04-20 | 1989-05-02 | Nuclear Assurance Corporation | Spent nuclear fuel shipping basket and cask |
JPH01237499A (en) * | 1988-03-18 | 1989-09-21 | Mitsubishi Heavy Ind Ltd | Basket or radioactive material transport vessel |
DE19734166A1 (en) * | 1997-08-07 | 1999-02-11 | Siemens Ag | Transport container for spent nuclear reactor fuel elements |
JP3150669B2 (en) * | 1999-09-02 | 2001-03-26 | 三菱重工業株式会社 | Cask |
-
2002
- 2002-12-24 DE DE50211653T patent/DE50211653D1/en not_active Expired - Lifetime
- 2002-12-24 EP EP02028964A patent/EP1434239B1/en not_active Expired - Lifetime
- 2002-12-24 AT AT02028964T patent/ATE385607T1/en not_active IP Right Cessation
-
2003
- 2003-12-10 JP JP2003411999A patent/JP4815100B2/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
JP2004205503A (en) | 2004-07-22 |
EP1434239B1 (en) | 2008-02-06 |
ATE385607T1 (en) | 2008-02-15 |
EP1434239A1 (en) | 2004-06-30 |
DE50211653D1 (en) | 2008-03-20 |
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