Published 2009 | Version v1
Journal article Metadata-only

Radiation release characterization of PWR spent fuel assemblies generated from Korean Nuclear Power Plants

Creators

  • 1. Department of Energy and Environment, Dongguk University 707, Seokjang-dong, Gyeongju Gyeongbuk, 780-714, (Korea, Republic of)

Description

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 10(5) times higher than the neutron dose. (author)

Availability note (English)

Also available online from http://ntrp.vinca.rs

Additional details

Identifiers

URL
http://ntrp.vinca.rs;

Publishing Information

Journal Title
Nuclear Technology and Radiation Protection
Journal Volume
24
Journal Issue
3
Journal Page Range
p. 183-187
ISSN
1451-3994

INIS

Country of Publication
Serbia
Country of Input or Organization
Serbia
INIS RN
41035126
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; CONCENTRATION RATIO; EVALUATION; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL ASSEMBLIES; GAMMA RADIATION; M CODES; MONTE CARLO METHOD; NEUTRONS; O CODES; PHOTONS; PWR TYPE REACTORS; RADIATION DOSE DISTRIBUTIONS; RADIATION DOSES; REPUBLIC OF KOREA; SOURCE TERMS; SPENT FUEL ELEMENTS; WESTINGHOUSE STANDARD REACTOR
Descriptors DEC
ASIA; BARYONS; BOSONS; CALCULATION METHODS; COMPUTER CODES; DATA; DEVELOPING COUNTRIES; DIMENSIONLESS NUMBERS; DOSES; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; EVALUATION; FERMIONS; FUEL ELEMENTS; HADRONS; INFORMATION; IONIZING RADIATIONS; MASSLESS PARTICLES; NUCLEONS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 refs., 4 figs., 3 tabs.