Published May 1981
| Version v1
Journal article
TEMPELS code used for pellet-cladding interaction analysis
Creators
- 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)
- 2. Maribor Univ. (Yugoslavia)
Description
A bi-dimensional finite element code for the thermal and stress analysis of ceramic pellet/metal cladding tube interactions in nuclear reactor fuel elements is described. Results obtained with the programme for a specific problem are given and show an increase of hoop stresses in the cladding tube up to 200 MPa during the postulated interaction. Thus the yield stress limit of irradiated Zircaloy, assumed to be about 520 MPa, has not been approached and the pin structure may be considered safe and reliable with given loading. (U.K.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng.
- Journal Volume
- 22
- Journal Issue
- 3
- Series
- Nucl. Eng.
- Journal Page Range
- 73-75
- ISSN
- 0368-2595
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 13714912
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CERAMICS; COMPRESSION; FINITE ELEMENT METHOD; FUEL CANS; FUEL ELEMENTS; FUEL PELLETS; FUEL PINS; FUEL-CLADDING INTERACTIONS; HIGH PRESSURE; PRESSURE DEPENDENCE; QUALITY ASSURANCE; STRESS ANALYSIS; STRESSES; T CODES; THERMAL ANALYSIS; TWO-DIMENSIONAL CALCULATIONS; VERY HIGH PRESSURE; ZIRCALOY
- Descriptors DEC
- ALLOYS; COMPUTER CODES; NUMERICAL SOLUTION; REACTOR COMPONENTS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS