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Development of safety evaluation method for dry storage of spent nuclear fuel: 1. Investigation of the current status

Jeong, Chan Woo; Cheong, Jae Hak
Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)2003

[en] This is the result of the project 'Development of Regulatory Technology for Radioactive Waste', and provides the state-of-the-art report on the dry storage of spent nuclear fuel. Currently 28 sites in the US have been allowed to load irradiated fuel assemblies into dry storage systems. Twelve sites have site-specific licenses and the remained sixteen sites have general licensees. The design features and basic concepts of fifteen cask models granted for general license were analyzed. As standard safety factors for ensuring the safety of dry storage facilities, totally twenty one factors were derived as: (1) site characteristics, (2) major design requirements, (3) structural integrity, (4) materials, (5) decay heat, (6) fire protection, (7) shielding, (8) criticality, (9) confinement, (10) handling of spent fuel, (11) physical protection and security, (12) operating procedure, (13) test and maintenance, (14) radwaste management, (15) radiation protection, (16) accident analysis, (17) auxiliary and/or service systems, (18) technical specifications and limiting conditions for operation, (19) quality assurance, (20) decommissioning, (21) retrievability. Furthermore, a draft classification system for categorizing safety classes of structures, systems, and components important to safety, for both metal and concrete casks. Licensing procedures, requested licensing documents, and related regulatory guides of the US NRC were surveyed and analyzed. In addition similar case studies were performed for Germany and Japan. Totally nine technical issues including 'impact of temperature to long-term integrity' were derived. In addition, seventeen Interim Staff Guidances issued by the Spent Fuel Project Office were analyzed for gathering information on the United States' recent regulatory issues. In relation to BUC(Burn-up Credit) issue, national application practices and application levels of the BUC in twenty countries were analyzed for each step of spent fuel management such as transport, storage, reprocessing, and disposal. As a result of this term's research and development, at last, a series of technical issues and regulatory issues were proposed to be include in the next term's work scope

Primary Subject

MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES (S12)

Source

Aug 2003; 424 p; Also available from KINS; 268 refs, 65 figs, 97 tabs

Record Type

Report

Report Number

KINS/RR--197

Country of publication

Korea, Republic of

Descriptors (DEI)

DESIGN, DRY STORAGE, FUEL ASSEMBLIES, RADIOACTIVE WASTES, SAFETY, SPENT FUELS

Descriptors (DEC)

ENERGY SOURCES, FUELS, MATERIALS, NUCLEAR FUELS, RADIOACTIVE MATERIALS, REACTOR MATERIALS, STORAGE, WASTES

LanguageLanguage

Korean

Reference NumberReference Number

39123590

INIS VolumeINIS Volume

INIS IssueINIS Issue

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