Published 1992 | Version v1
Miscellaneous Metadata-only

Shielding evaluation for PWR spent fuel shipping cask

Creators

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

This study presents to conform the shielding integrity of the KSC-4 shipping cask for loading 4 PWR fuel assemblies. The source terms of the KSC-4 shipping cask was calculated by using the ORIGEN-2 computer code. The shielding analysis was carried by the ANISN computer code. The compared results between the calculated and the measured dose rate shows that the shielding integrity of the KSC-4 cask was verified within the allowable values specified as the transport regulations

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
706 p.
Journal Page Range
p. 519-526

Conference

Title
1992 spring meeting of the KNS
Dates
29-30 May 1992
Place
Kori (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38022695
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CASKS; DOSE RATES; FUEL ASSEMBLIES; O CODES; PWR TYPE REACTORS; SHIELDING; SOURCE TERMS; SPENT FUELS; TRANSPORT
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 2 figs, 4 tabs