Light water reactor fuel analysis code FEMAXI-7; model and structure
Creators
- 1. Japan Atomic Energy Agency, Safety Research Center, Tokai, Ibaraki (Japan)
- 2. ITOCHU Techno-Solutions Corporation, Tokyo (Japan)
Description
A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in both normal conditions and anticipated transient conditions. This code is an advanced version which has been produced by incorporating the former version FEMAXI-6 with numerous functional improvements and extensions. In FEMAXI-7, many new models have been added and parameters have been clearly arranged. Also, to facilitate effective maintenance and accessibility of the code, modularization of subroutines and functions have been attained, and quality comment descriptions of variables or physical quantities have been incorporated in the source code. With these advancements, the FEMAXI-7 code has been upgraded to a versatile analytical tool for high burnup fuel behavior analyses. This report describes in detail the design, basic theory and structure, models and numerical method, and improvements and extensions. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-data-code-2010-035
Files
System files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 378 p.
- Report number
- JAEA-Data/Code--2010-035
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43005507
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; CORROSION; F CODES; FISSION PRODUCT RELEASE; FUEL PELLETS; MATHEMATICAL MODELS; NUCLEAR FUELS; NUMERICAL ANALYSIS; THERMAL HYDRAULICS; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES; ENERGY SOURCES; FLUID MECHANICS; FUELS; HYDRAULICS; MATERIALS; MATHEMATICS; MECHANICS; PELLETS; REACTOR MATERIALS; REACTORS
Optional Information
- Notes
- 127 refs., 83 figs., 12 tabs.