Raiko et al., 2005 - Google Patents
Finnish concept for spent nuclear fuel disposalRaiko et al., 2005
View PDF- Document ID
- 9999582324263918498
- Author
- Raiko H
- Jalonen T
- Kukkola T
- Salo J
- Publication year
External Links
Snippet
In Finland, the spent nuclear fuel will be emplaced in the bedrock at a target depth interval of 400-500 metres. Posiva Oy is the company responsible for high active nuclear waste management in Finland. Currently, an ONKALO URL (Underground Research Laboratory) …
- 239000002915 spent fuel radioactive waste 0 title abstract description 53
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
- G21F5/008—Containers for fuel elements
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/24—Disposal of liquid waste by storage in the ground; by storage under water, e.g. in ocean
-
- 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
- G21F5/06—Details of, or accessories to, the containers
- G21F5/12—Closures for containers; Sealing arrangements
-
- 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
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
-
- 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
- G21F5/06—Details of, or accessories to, the containers
- G21F5/14—Devices for handling containers or shipping-casks, e.g. transporting devices loading and unloading, filling of containers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
-
- 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
- G21F1/00—Shielding characterised by the composition of the materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- 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
- G21F7/00—Shielded cells or rooms
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Baumgartner et al. | Engineering for a disposal facility using the in-room emplacement method | |
Raiko et al. | Finnish concept for spent nuclear fuel disposal | |
Matteo et al. | Status of Progress Made Toward Preliminary Design Concepts for the Inventory in Select Media for DOE-Managed HLW/SNF | |
Fries et al. | The Swiss concept for the disposal of spent fuel and vitrified HLW | |
Saanio et al. | Preliminary design of the repository. Stage 2 | |
Huumarkangas | Posiva's deep geological repository for spent nuclear fuel | |
Lauridsen | Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment | |
Pettersson et al. | Development of the Swedish deep repository for spent nuclear fuel in crystalline host rock | |
Smith | DECONTAMINATION AND DECOMMISSIONING OF THE MTR-603 HB-2 CUBICLEa | |
Doudou et al. | Approaches to evaluate and underpin the technical feasibility of the Belgian disposal concept | |
Moyer et al. | Baseline descriptions for LWR spent fuel storage, handling, and transportation | |
Garrett et al. | US graphite reactor D&D experience | |
Unterzuber et al. | Monitored Retrievable Storage conceptual system study: tunnel drywells | |
Biurrun et al. | Licensing of the National Repository for LILW Waste in Bulgaria–15609 | |
Hedman et al. | Design, construction and safety assessments for a repository in bedrock | |
Hedman | Management of Spent Nuclear Fuel in Sweden | |
AB | Plan 90 Costs for management of the radioactive waste from nuclear power production | |
Trevorrow et al. | Alternatives for Disposal of Raffinate from the TRUEX Process | |
Nolan et al. | Characterization Modeling and Remediation Method Selection to Support Remedial Design Solution Development for the Hanford 618-10 and 618-11 Burial Grounds | |
Garrett et al. | US graphite reactor D ampersand D experience | |
Heystee | Proposed deep geologic repository for low and intermediate-level radioactive waste at the Bruce site, Tiverton, Ontario | |
Code et al. | ACl 318 | |
McCall et al. | Conceptual design of an underground radioactive waste repository | |
CUMMINS | National Environmental Policy Act (NEPA) Source Guide for the Hanford Site September 1999 | |
Short et al. | Assessment of the Grouted IXC Monolith in Support of K East Basin Hazard Categorization |