Analysis of fuel behavior in power-ramp tests by FEMAXI-IV code
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Dept. of Fuel Safety Research
- 2. Korea Advanced Energy Research Inst., Daeduk (Republic of Korea)
Description
FEMAXI-IV is a computer code to analyze the thermal and mechanical behavior of a fuel rod during steady-state and transient conditions. FEMAXI-IV calculates the stress and strain distributions in the fuel and cladding due to the pellet-cladding mechanical interaction using the two-dimensional axisymmetric finite element method. It also calculates the fission gas release using a simplified physical model. Two of the most important phenomena relating to cladding failure are the pellet-cladding mechanical interaction and the release of fission gas into the gap between fuel and cladding. Using the FEMAXI-IV code, the fuel behavior obtained in the Studsvik power ramp experiments has been analyzed and the several important parameters affecting cladding failure have been studied. (author)
Additional details
Publishing Information
- Journal Title
- Res Mechanica
- Journal Volume
- 25
- Journal Issue
- 2
- Series
- Res Mech.
- Journal Page Range
- 101-128
- ISSN
- 0143-0084
- CODEN
- RESMD
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 20019149
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- F CODES; FAILURES; FINITE ELEMENT METHOD; FISSION PRODUCT RELEASE; FUEL RODS; FUEL-CLADDING INTERACTIONS; STEADY-STATE CONDITIONS; STRAINS; STRESSES; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; FUEL ELEMENTS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS