Published February 2010 | Version v1
Journal article Metadata-only

Application of Multigroup Monte-Carlo Method for Reactor Shielding Design

Creators

  • 1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing (China)

Description

Multigroup MCNP code calculation was made for the 10 MW High-Temperature Gas-Cooled Reactor in Tsinghua University. Multigroup cross-sections were got from the DCL-75/BUGLE-80 cross-section library, using discrete angular representation and equally probable step function representation to approach real angular distribution. The results show that the multigroup MCNP and SN procedure DOT meet well. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
44
Journal Issue
2
Journal Page Range
p. 197-200
ISSN
1000-6931

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
43084974
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ANGULAR DISTRIBUTION; COMPUTER CALCULATIONS; CROSS SECTIONS; DATA BASE MANAGEMENT; DESIGN; EDUCATIONAL FACILITIES; FUNCTIONS; HTGR TYPE REACTORS; M CODES; MONTE CARLO METHOD; MULTIGROUP THEORY; NUCLEAR DATA COLLECTIONS; SHIELDING
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; DISTRIBUTION; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MANAGEMENT; NEUTRON TRANSPORT THEORY; REACTORS; TRANSPORT THEORY

Optional Information

Notes
3 figs., 5 refs.