Published May 2002 | Version v1
Miscellaneous Metadata-only

Free drop test for CASTOR/KN-12 radioactive material transportation cask

Creators

  • 1. KAERI, Taejon (Korea, Republic of)
  • 2. KHNP, Seoul (Korea, Republic of)
  • 3. Chungnam National Univ., Taejon (Korea, Republic of)

Description

Spent nuclear fuel transportation cask called CASTOR/KN-12 is developed due to the saturation of spent fuel storage pool in some PWR nuclear power plants. Transportation contents of this cask is 12 spent nuclear fuel assemblies considering high burn-up and high enrichment. Free drop impact tests were performed according to the test requirements of domestic MOST notice and IAEA ST-1. Structural safety were evaluated by means of dropping a 1/3 scaled model of this cask from 9 m height to unyielding surface or from 1 m height to pin. The verification data for computer calculation were produced by measuring the displacements, accelerations and strains and the structural behavior during the drop impact moment was evaluated by experimented method

Part of:
Proceedings of the KNS-KARP Joint spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS-KARP Joint spring meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[11 p.]

Conference

Title
2002 joint spring meeting of the KNS-KARP
Dates
23-24 May 2002
Place
Gwangju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
34009897
Subject category
S42: ENGINEERING; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CASKS; COMPUTER CALCULATIONS; IMPACT TESTS; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE STORAGE; SATURATION; SPENT FUELS
Descriptors DEC
CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MANAGEMENT; MATERIALS; MATERIALS TESTING; MECHANICAL TESTS; NUCLEAR FUELS; POWER REACTORS; RADIOACTIVE WASTE MANAGEMENT; REACTOR MATERIALS; REACTORS; STORAGE; TESTING; THERMAL REACTORS; WASTE MANAGEMENT; WASTE STORAGE; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 17 figs, 3 tabs