Published June 1994
| Version v1
Journal article
Ppercase(femaxi-iv): a computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods
Creators
- 1. Japan Atomic Energy Research Institute, Tokaimura (Japan)
- 2. Century Research Center Corporation, Tokyo (Japan)
Description
Ppercase(femaxi-iv) is a computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods during steady-state and transient conditions. The main purpose of ppercase(femaxi-iv) is to calculate the stress and strain distributions in the fuel and cladding due to the pellet-cladding mechanical interaction, and the fission gas release rate during operations, especially power transients. The capability of ppercase(femaxi-iv) was extensively tested with a number of experimental results obtained in some international fuel irradiation programs. This paper provides a general description of the various models involved in ppercase(femaxi-iv) and some results of applications on the experimental data. ((orig.))
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 148
- Journal Issue
- 1
- Journal Page Range
- p. 41-52.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26008511
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Computer Program Description
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTER PROGRAM DOCUMENTATION; F CODES; FISSION PRODUCT RELEASE; FUEL RODS; FUEL-CLADDING INTERACTIONS; MECHANICAL PROPERTIES; PWR TYPE REACTORS; STRESS ANALYSIS; TRANSIENTS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FUEL ELEMENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS