Published August 2001 | Version v1
Report Open

A structural analysis on the KN-12 spent nuclear fuel transport casks

Creators

  • 1. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
  • 2. Chungnam National Univ., Taejon (Korea, Republic of)

Description

In this study, safety of the spent nuclear fuel cask KN-12 which is developed in 2000 is evaluated for hypothetical accidents conditions such as free drop, puncture, fire accident and water immersion. Finite element code ABAQUS/Explicit is used to compare with safety analysis report of the GNB in which analysis is performed with LS-DYNA3D for hypothetical accident conditions. Through this study, the safety of KN-12 is evaluated by comprehensive structural analysis. The capability and technological advancement of Korean community on the analysis and structural assessment of the cask will be improved. Also people's anxiety about radioactive dangers will be eliminated

Availability note (English)

Available from INIS in electronic form; Also available from KINS

Files

37110608.pdf

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Additional details

Publishing Information

Imprint Pagination
69 p.
Report number
KINS/HR--407

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
37110608
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
Descriptors DEI
A CODES; ACCIDENTS; CASKS; RADIATION PROTECTION; RADIOACTIVE MATERIALS; SAFETY ANALYSIS; SPENT FUELS; TRANSPORT
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS

Optional Information

Notes
15 refs, 58 figs, 6 tabs