Published 1994 | Version v1
Report Open

Program MCU for the Monte-Carlo calculation of neutron-physical characteristics of nuclear reactors. Programming language NCGSIM for the geometric module NCG

Creators

Description

The paper describes the language MCGSIM for description a geometry. It was elaborated for combinatorial geometry module Mcg. This module belongs to the program Mc for calculating the flux by Monte-Carlo method. It includes opportunities of the module Sc. There are many additional opportunities for describing very complex systems

Availability note (English)

Available from INIS in electronic form

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Additional details

Additional titles

Original title (Russian)
Программа MCU для расчета методом Монте-Карло нейтронно-физических характеристик ядерных реакторов. Язык описания геометрии NCGSIM для геометрического модуля NCG

Publishing Information

Imprint Pagination
30 p.
Report number
IAE--5771/5

INIS

Country of Publication
Russian Federation
Country of Input or Organization
Russian Federation
INIS RN
29038038
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ALGORITHMS; COMPUTER CALCULATIONS; GEOMETRY; M CODES; MONTE CARLO METHOD; NEUTRON TRANSPORT; PROGRAMMING; PROGRAMMING LANGUAGES; REACTOR CELLS
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT

Optional Information

Notes
8 figs.