Published May 1997 | Version v1
Journal article Metadata-only

Two dimensional geometry thermal group Monte Carlo program MCTGP-2D

Creators

  • 1. Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

Description

MCTGP-2D, a modified version of thermal-group Monte Carlo program, can run on the computer AST 486-386. It is used to calculate the thermal neutron flux and the thermal utilization for two dimensional geometry consisting of circle, ellipse, triangle, rectangle and quadrilateral. MCTGP-2D also gives graphic display of the calculated geometry structure

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
31
Journal Issue
3
Journal Page Range
p. 234-237.
ISSN
1000-6931
CODEN
YKJIEZ

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
28053638
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Descriptors DEI
COMPUTER GRAPHICS; GEOMETRY; GROUP CONSTANTS; M CODES; MICROCOMPUTERS; MONTE CARLO METHOD; NEUTRON FLUX; THERMAL NEUTRONS; THERMAL UTILIZATION; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
BARYONS; CALCULATION METHODS; COMPUTER CODES; COMPUTERS; CROSS SECTIONS; DIGITAL COMPUTERS; ELEMENTARY PARTICLES; FERMIONS; HADRONS; MATHEMATICS; NEUTRONS; NUCLEONS; RADIATION FLUX