Published March 2011 | Version v1
Report Restricted

Light water reactor fuel analysis code FEMAXI-7; model and structure

  • 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

Restricted

The record is publicly accessible, but files are restricted to users with access.

System files (646.3 kB)

Name Size Download all

Additional details

Publishing Information

Imprint Pagination
378 p.
Report number
JAEA-Data/Code--2010-035

Optional Information

Notes
127 refs., 83 figs., 12 tabs.