GB1444479A - Radioactive waste storage - Google Patents
Radioactive waste storageInfo
- Publication number
- GB1444479A GB1444479A GB1558274A GB1558274A GB1444479A GB 1444479 A GB1444479 A GB 1444479A GB 1558274 A GB1558274 A GB 1558274A GB 1558274 A GB1558274 A GB 1558274A GB 1444479 A GB1444479 A GB 1444479A
- Authority
- GB
- United Kingdom
- Prior art keywords
- cask
- wastes
- storage
- april
- carbon steel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- 239000002901 radioactive waste Substances 0.000 title 1
- 239000002775 capsule Substances 0.000 abstract 2
- 239000000463 material Substances 0.000 abstract 2
- 229910052751 metal Inorganic materials 0.000 abstract 2
- 239000002184 metal Substances 0.000 abstract 2
- 239000011435 rock Substances 0.000 abstract 2
- 239000002699 waste material Substances 0.000 abstract 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 1
- 229910000975 Carbon steel Inorganic materials 0.000 abstract 1
- 229910001209 Low-carbon steel Inorganic materials 0.000 abstract 1
- 239000004698 Polyethylene Substances 0.000 abstract 1
- 230000015572 biosynthetic process Effects 0.000 abstract 1
- 239000010962 carbon steel Substances 0.000 abstract 1
- 239000011248 coating agent Substances 0.000 abstract 1
- 238000000576 coating method Methods 0.000 abstract 1
- 238000001816 cooling Methods 0.000 abstract 1
- 230000007797 corrosion Effects 0.000 abstract 1
- 238000005260 corrosion Methods 0.000 abstract 1
- 229910002804 graphite Inorganic materials 0.000 abstract 1
- 239000010439 graphite Substances 0.000 abstract 1
- 239000002927 high level radioactive waste Substances 0.000 abstract 1
- 229910052745 lead Inorganic materials 0.000 abstract 1
- 150000002739 metals Chemical class 0.000 abstract 1
- 230000035515 penetration Effects 0.000 abstract 1
- -1 polyethylene Polymers 0.000 abstract 1
- 229920000573 polyethylene Polymers 0.000 abstract 1
- 230000001737 promoting effect Effects 0.000 abstract 1
- 230000005855 radiation Effects 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
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)
Abstract
1444479 Shielded containers UNITED STATES ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION 9 April 1974 [17 April 1973] 15582/74 Heading B4Q [Also in Divisions G4-G6] A storage cask for high-level radioactive wastes housed in a container 10 comprises a thick-walled metal capsule 11 with a plug 13 sealed in place with a deep penetration weld 12, the thickness of the walls of the capsule being sufficient to reduce radiation to a tolerable level and to permit storage of the cask out-of-doors. Natural convection of air over the cask removes the decay heat. Low carbon steel is a suitable material for the cask, preferably with 0À25 wt. per cent Cu having been added to improve corrosion resistance by promoting the formation of a tightly held oxide coating. In place of carbon steel, other metals such as Pb or U could be utilized. To promote the natural convection around the cask, this is supported on precast saddles 14. Such casks are preferably stored in a dry, arid climate for 150 years or longer, after which they can be placed in a hard rock mine where the thermal conductivity of the rock will be sufficient for excessive temperature increases in the wastes not to occur. If the wastes are solely from Pm-recycle pressurized-water reactors, the high neutron dose rate around the cask must be reduced either by surrounding the cask in its storage position with crushed graphite (Fig. 2, not shown) or by placing cooling fins on the cask and employing neutron shielding material such as polyethylene between the fins (Fig. 3, not shown).
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US00351911A US3828197A (en) | 1973-04-17 | 1973-04-17 | Radioactive waste storage |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1444479A true GB1444479A (en) | 1976-07-28 |
Family
ID=23382946
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1558274A Expired GB1444479A (en) | 1973-04-17 | 1974-04-09 | Radioactive waste storage |
Country Status (6)
| Country | Link |
|---|---|
| US (1) | US3828197A (en) |
| JP (1) | JPS5035600A (en) |
| CA (1) | CA1006631A (en) |
| DE (1) | DE2418518A1 (en) |
| FR (1) | FR2226730B1 (en) |
| GB (1) | GB1444479A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2139407A (en) * | 1981-02-07 | 1984-11-07 | Wiederaufarbeitung Von Kernbre | Device for closing a storage container for radioactive materials |
| DE3403541A1 (en) * | 1984-02-02 | 1985-08-08 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | METHOD AND DEVICE FOR AUTOMATICALLY AND / OR REMOTELY WELDING THE LID AND / OR THE FLOOR WITH THE SHEATH OF CONTAINERS FOR THE RECEIVING OF RADIOACTIVE FUEL ELEMENTS AND HARDENING |
Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3983050A (en) * | 1975-02-07 | 1976-09-28 | The United States Of America As Represented By The United States Energy Research And Development Administration | Method for storage of solid waste |
| AT338387B (en) * | 1975-06-26 | 1977-08-25 | Oesterr Studien Atomenergie | METHOD OF EMBEDDING RADIOACTIVE AND / OR TOXIC WASTE |
| US4040480A (en) * | 1976-04-15 | 1977-08-09 | Atlantic Richfield Company | Storage of radioactive material |
| DE2726335C2 (en) * | 1977-06-10 | 1984-12-13 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Container unit for radioactive waste that can be used for final disposal |
| DE2740933C2 (en) * | 1977-09-10 | 1982-11-25 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Transport and storage containers for radioactive substances, especially irradiated nuclear reactor fuel elements |
| DE2915376C2 (en) * | 1979-04-14 | 1984-02-02 | Transnuklear Gmbh, 6450 Hanau | Container combination for the transport and storage of spent fuel elements from nuclear reactors |
| DE2942092C2 (en) * | 1979-10-18 | 1985-01-17 | Steag Kernenergie Gmbh, 4300 Essen | Final storage containers for radioactive waste, in particular irradiated nuclear reactor fuel elements |
| DE3012310A1 (en) * | 1980-03-29 | 1981-10-08 | Transnuklear Gmbh, 6450 Hanau | INSERT BASKET FOR RADIOACTIVE MATERIAL IN TRANSPORT AND / OR STORAGE CONTAINERS |
| DE3103557A1 (en) * | 1981-02-03 | 1982-12-09 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | "TRANSPORT AND STORAGE CONTAINERS FOR RADIOACTIVE WASTE" |
| CH658333A5 (en) * | 1981-12-22 | 1986-10-31 | Wiederaufarbeitung Von Kernbre | CONTAINERS FOR LONG-TERM STORAGE OF RADIOACTIVE MATERIAL, IN PARTICULAR Spent NUCLEAR FUEL. |
| US4700863A (en) * | 1986-01-09 | 1987-10-20 | The United States Of America As Represented By The United States Department Of Energy | Seal welded cast iron nuclear waste container |
| US4803042A (en) * | 1987-11-23 | 1989-02-07 | Westinghouse Electric Corp. | Nuclear reactor core component shipping container |
| US5102615A (en) * | 1990-02-22 | 1992-04-07 | Lou Grande | Metal-clad container for radioactive material storage |
| US10210961B2 (en) * | 2012-05-11 | 2019-02-19 | Ge-Hitachi Nuclear Energy Americas, Llc | System and method for a commercial spent nuclear fuel repository turning heat and gamma radiation into value |
| US20160019991A1 (en) * | 2014-07-16 | 2016-01-21 | Westinghouse Electric Company Llc | Source of electricity derived from a spent fuel cask |
| DE102016010903A1 (en) * | 2016-09-08 | 2018-03-08 | Jürgen Himbert | Container combination and method for removing radioactive substances |
| CN109119178B (en) * | 2018-10-22 | 2022-12-06 | 天津市万木辐射防护工程有限公司 | Lead box for storing radioactive isotope medicines |
| CN109659055A (en) * | 2018-11-04 | 2019-04-19 | 青岛东卡环保工程技术有限公司 | Low-level radioactive waste compresses steel drum in a kind of novel 170L |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2928948A (en) * | 1955-05-23 | 1960-03-15 | Herman I Silversher | Laminar ray resistant materials |
| BE583252A (en) * | 1958-10-17 | |||
| US3046403A (en) * | 1959-04-17 | 1962-07-24 | Babcock & Wilcox Co | Device for the storage of a heat evolving material |
| US3262274A (en) * | 1962-09-27 | 1966-07-26 | Mobil Oil Corp | Containment of radioactive wastes |
| GB1054219A (en) * | 1965-04-15 | |||
| US3466445A (en) * | 1967-10-06 | 1969-09-09 | Atomic Energy Commission | Container for radioactive fuel elements |
| US3751669A (en) * | 1971-05-24 | 1973-08-07 | Nl Industries Inc | Radiation shielding means joint and method of making same |
-
1973
- 1973-04-17 US US00351911A patent/US3828197A/en not_active Expired - Lifetime
-
1974
- 1974-04-08 CA CA197,004A patent/CA1006631A/en not_active Expired
- 1974-04-09 GB GB1558274A patent/GB1444479A/en not_active Expired
- 1974-04-16 JP JP49043227A patent/JPS5035600A/ja active Pending
- 1974-04-17 FR FR7413408A patent/FR2226730B1/fr not_active Expired
- 1974-04-17 DE DE2418518A patent/DE2418518A1/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2139407A (en) * | 1981-02-07 | 1984-11-07 | Wiederaufarbeitung Von Kernbre | Device for closing a storage container for radioactive materials |
| US4638134A (en) * | 1981-02-07 | 1987-01-20 | Deutsche Gesellschaft | Device for evacuating, filling and closing final storage containers for radioactive materials |
| DE3403541A1 (en) * | 1984-02-02 | 1985-08-08 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | METHOD AND DEVICE FOR AUTOMATICALLY AND / OR REMOTELY WELDING THE LID AND / OR THE FLOOR WITH THE SHEATH OF CONTAINERS FOR THE RECEIVING OF RADIOACTIVE FUEL ELEMENTS AND HARDENING |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2226730A1 (en) | 1974-11-15 |
| US3828197A (en) | 1974-08-06 |
| JPS5035600A (en) | 1975-04-04 |
| CA1006631A (en) | 1977-03-08 |
| FR2226730B1 (en) | 1977-10-14 |
| DE2418518A1 (en) | 1974-11-07 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| GB1444479A (en) | Radioactive waste storage | |
| ES258034U (en) | Transport and storage vessel for radioactive materials | |
| JPH032695A (en) | Radiation shielding material with high heat removal efficiency | |
| GB1196269A (en) | Shipping Container for Radioactive Materials | |
| ZA785057B (en) | Transport or storage containers for radioactive materials,particularly irradiated fuel elements of nuclear reactors | |
| GB1511620A (en) | Nuclear reactor | |
| GB1422018A (en) | Packaging for conveying radio active substances such as irradiated fuel elements having high afterheat | |
| GB1311069A (en) | Shipping cask | |
| EP4332992A1 (en) | Spent nuclear fuel canister having high thermal conductivity and self-sealing function | |
| US3781189A (en) | Spent nuclear fuel shipping casks | |
| JPS63760B2 (en) | ||
| US4261756A (en) | Lead alloy and granulate concrete containing the same | |
| GB1222189A (en) | Improvements in and relating to shielding containers | |
| JP3143856B2 (en) | Radioactive material storage container | |
| GB1055818A (en) | Transit flask for radioactive objects | |
| GB1054219A (en) | ||
| US20030165649A1 (en) | Repository disposal container | |
| ES8303796A1 (en) | Container for transporting and/or storing radioactive materials. | |
| Forsberg et al. | Characteristics and fabrication of cermet spent nuclear fuel casks: ceramic particles embedded in steel | |
| RU94044509A (en) | Method and fast neutrons reactor for radioactive isotopes production | |
| GB1204300A (en) | Radioisotope heat source | |
| JPS5930474Y2 (en) | Container for transporting spent nuclear fuel | |
| Blomeke et al. | Projected shipments of special nuclear material and wastes by the nuclear power industry | |
| JPS61195398A (en) | Transport vessel for spent nuclear fuel | |
| GB897443A (en) | Improvements in or relating to nuclear reactors |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| CSNS | Application of which complete specification have been accepted and published, but patent is not sealed |