Axisym finite element code: modifications for pellet-cladding mechanical interaction analysis
Description
Local strain concentrations in nuclear fuel rods are known to be potential sites for failure initiation. Assessment of such strain concentrations requires a two-dimensional analysis of stress and strain in both the fuel and the cladding during pellet-cladding mechanical interaction. To provide such a capability in the FRAP (Fuel Rod Analysis Program) codes, the AXISYM code (a small finite element program developed at the Idaho National Engineering Laboratory) was modified to perform a detailed fuel rod deformation analysis. This report describes the modifications which were made to the AXISYM code to adapt it for fuel rod analysis and presents comparisons made between the two-dimensional AXISYM code and the FRACAS-II code. FRACAS-II is the one-dimensional (generalized plane strain) fuel rod mechanical deformation subcode used in the FRAP codes. Predictions of these two codes should be comparable away from the fuel pellet free ends if the state of deformation at the pellet midplane is near that of generalized plane strain. The excellent agreement obtained in these comparisons checks both the correctness of the AXISYM code modifications as well as the validity of the assumption of generalized plane strain upon which the FRACAS-II subcode is based
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.Files
10449487.pdf
Files
(8.7 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:4da20e4cd30d5a120c7c2d133fbf87cc
|
8.7 MB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 88 p.
- Report number
- CDAP-TR--78-041
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10449487
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- A CODES; DEFORMATION; FINITE ELEMENT METHOD; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; MATHEMATICAL MODELS; STRAINS; STRESSES; WATER COOLED REACTORS
- Descriptors DEC
- COMPUTER CODES; FUEL ELEMENTS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS