Thermal Test and Analysis for KSC-7 Cask Development

Year

1995

Author(s)

J.C. Lee - KAERI

K.S. Bang - KAERI

H.Y. Lee - Korea Atomic Energy Research Institute (KAERI)

S.H. Cho - Korea Atomic Energy Research Institute (KAERI)

J.B. Do - Korea Atomic Energy Research Institute (KAERI)

File Attachment

617.PDF1.45 MB

Abstract

All shipping casks for spent nuclear fuels should be evaluated for their thermal integrity in accordance with the design criteria prescribed in IAEA (IAEA a and b) and Korea internal regulations. The objective of this paper is to verify the thermal integrity for dry shipment of the KSC-7 cask Wider normal transport conditions. The cask was designed to transport seven PWR spent-fuel assemblies with a bumup of 50,000 MWD/MTU and a cooling time of 1.5 years.