Open AccessRadiation release characterization of PWR spent fuel assemblies generated from Korean nuclear power plants
Author(s) -
Hyun Joo Moon
Publication year - 2009
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp0903183m
Subject(s) - nuclear engineering , spent nuclear fuel , nuclear power plant , environmental science , monte carlo method , radiation , neutron , nuclear power , spent fuel pool , nuclear physics , materials science , effective dose (radiation) , nuclear medicine , physics , medicine , engineering , mathematics , statistics
Spent nuclear fuel should be kept under safe management until it is disposed of permanently. Because of this, it is important to understand its radiation release characteristics. In this paper, the Monte Carlo method is applied to evaluate the radiation release characteristics of two types of PWR spent fuel assembly generated from the operating plants in Korea: Westinghouse and Korea Standard Nuclear Power Plant. The source terms were calculated using ORIGEN-ARP. The neutron and photon (or gamma) dose distributions along the vertical and horizontal directions of each spent fuel assembly were evaluated using MCNPX code. Compared with the two dose distributions, the photon dose was found to be about 105 times higher than the neutron dose