Open AccessPreliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions
Author(s) -
Tae-Man Kim,
Ho-Seog Dho,
Chun-Hyung Cho,
Jae-Hun Ko
Publication year - 2017
Publication title -
bangsaseong pyegi'mul haghoeji/journal of nuclear fuel cycle and waste technology
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.198
H-Index - 3
eISSN - 2288-5471
pISSN - 1738-1894
DOI - 10.7733/jnfcwt.2017.15.4.391
Subject(s) - cask , spent nuclear fuel , electromagnetic shielding , environmental science , nuclear engineering , waste management , materials science , engineering , composite material