Thermal and stress analysis of a fuel rod research project 277
Description
The purpose of this investigation was to perform an analytical evaluation of a postulated loss of coolant incident in a large pressurized water reactor. A coupled thermal and stress finite element analysis of a fuel rod subjected to a hypothetical blow-down transient was carried out. The effect of two gap conditions and two initial stress states on the response of the fuel rod was studied. Both one-dimensional and three-dimensional models were investigated. To study the heat transfer in the gap region one assumes a conductive mode of heat transfer in the gap characterized by an equivalent thermal conductivity, which is dependent on the current gap width. Accordingly, coupled analysis procedure and computational scheme were established. A mesh generation computer program was developed for the three-dimensional model
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A09/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 183 p.
- Report number
- EPRI--277
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13664697
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; DEFORMATION; FINITE ELEMENT METHOD; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY; STRAINS; STRESS ANALYSIS; THERMAL STRESSES; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; FUEL ELEMENTS; NUMERICAL SOLUTION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS