Modelling of pellet-cladding interaction in thermal reactor fuel pins using the Sleuth computer code
Description
This Paper describes the modelling of pellet-cladding mechanical interaction (PCI) in thermal reactor fuel pins using the Sleuth Computer code. The code is based on the fundamental physical mechanisms causing PCI (differential thermal expansion, fuel swelling, cladding creep-down, etc.) coupled with an estimate of strain concentrations over fuel cracks. It uses the classical 1 1/2 dimensional method which subdivides the fuel both axially and radially. While Sleuth was originally developed to predict PCI failure/survival, it has evolved into a general fuel performance code. The latest version, Sleuth 86, which is a modular form with mnemonic variable names, has proved to be an ideal vehicle for testing new sub-models which have been required as the experimental data base has been expanded. (author)
Additional details
Publishing Information
- Journal Title
- Nuclear Energy
- Journal Volume
- 29
- Journal Issue
- 2
- Series
- Nucl. Energy.
- Journal Page Range
- 115-122
- ISSN
- 0140-4067
- CODEN
- NUEGA
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 21087765
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FUEL ELEMENT FAILURE; FUEL PINS; FUEL-CLADDING INTERACTIONS; MATHEMATICAL MODELS; S CODES; THERMAL REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION