Published March 1981
| Version v1
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MGCL-PROCESSOR: a computer code system for processing multigroup constants library MGCL
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment
Description
The computer code system MGCL-PROCESSOR has been developed for processing multigroup constants library MGCL. The processed data by this code system are used as a nuclear cross section set for neutron transport codes such as Monte Carlo codes, Sn codes or diffusion codes which are used for calculation of an effective multiplication factor and neutron flux distribution in a system. Therefore, this code system is now entried in computer code systems for evaluating nuclear criticality safety and for analysing nuclear reactor core performances. This document is a user's manual for the system. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
13660116.pdf
Files
(4.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 154 p.
- Report number
- JAERI-M--9396
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13660116
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CRITICALITY; DATA PROCESSING; GROUP CONSTANTS; M CODES; MANUALS; MULTIGROUP THEORY; NEUTRON TRANSPORT; NUMERICAL SOLUTION; PROGRAMMING; REACTOR SAFETY
- Descriptors DEC
- COMPUTER CODES; CROSS SECTIONS; DOCUMENT TYPES; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; SAFETY; TRANSPORT THEORY