Investigation of applicable methods on safety verification of disposal facilities and waste packages
- 1. Japan Nuclear Energy Safety Organization, Radioactive Waste Management and Transport Safety Division, Tokyo (Japan)
Description
In this project, three subjects about safety verification were investigated in FY 2010. For radioactive waste disposal facilities, verification items and methods for trench disposal facility and verification method of permeability on cover of pit disposal facility were studied. For waste packages subject to near surface pit disposal, adequacy of continuous use of the scaling factor and average radioactivity concentration, and a new method for verifying waste packages were investigated. Those results were finalized in consideration of the opinion from advisory panel, and publicly opened as JNES-SS reports. In FY 2010, four JNES-SS reports were published and all of these reports have been used as standards of safety verification on waste packages. The characteristics and verification procedures of wastes subject to near-surface trench disposal were also studied. For radioactive waste which will be returned from overseas, verification items and methods for receiving were investigated. Knowledge accumulated in this subject was reflected in the report on the safety of low level vitrified waste (CSD-B), which is written by Radioactive Waste Safety Subcommittee. All results have been utilized in safety verification on waste disposal facility and radioactive waste conducted by NISA and JNES. (author)
Additional details
Publishing Information
- Imprint Title
- Annual safety research report, JFY 2010
- Imprint Pagination
- 444 p.
- Journal Page Range
- p. 299-304
- Report number
- JNES-RE--2011-0001
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51066823
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- APPROPRIATE TECHNOLOGY; BENTONITE; CONCRETES; FUEL REPROCESSING PLANTS; HYDRAULIC CONDUCTIVITY; LOW-LEVEL RADIOACTIVE WASTES; PACKAGING; RADIOACTIVE WASTE DISPOSAL; REACTOR DISMANTLING; SAFETY; UNDERGROUND FACILITIES
- Descriptors DEC
- BUILDING MATERIALS; CLAYS; DEMOLITION; INORGANIC ION EXCHANGERS; ION EXCHANGE MATERIALS; MANAGEMENT; MATERIALS; MINERALS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; REACTOR LIFE CYCLE; SILICATE MINERALS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES
Optional Information
- Notes
- 1 ref., 2 figs.; This record replaces 46091749