Published December 1979
| Version v1
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Evaluation of fuel rod cladding strength in steady and non-steady reactor operation
Description
This contribution presents a means of interpreting post-irradiation examination results via the fuel rod modelling code IAMBUS. The model predicts the thermal and mechanical behaviour of fuel and cladding in steady and non-steady reactor operation. Great importance was given to investigation of the potential of fuel/clad mechanical interaction as a function of fuel pin design parameters and operating conditions
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Additional details
Publishing Information
- Imprint Title
- Specialists' meeting on theoretical modelling of LMFBR fuel pin behaviour. Summary report
- Imprint Pagination
- 183 p.
- Journal Page Range
- p. 59-63
- Report number
- IWGFR--31
Conference
- Title
- IAEA-IWGFR specialists' meeting on theoretical modelling of LMFBR fuel pin behaviour
- Dates
- 28 May - 1 Jun 1979
- Place
- Fontenay-aux-Roses (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33016329
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL RODS; FUEL-CLADDING INTERACTIONS; I CODES; MECHANICAL PROPERTIES; POST-IRRADIATION EXAMINATION; STEADY-STATE CONDITIONS
- Descriptors DEC
- COMPUTER CODES; FUEL ELEMENTS; REACTOR COMPONENTS
Optional Information
- Notes
- 1 ref., 7 figs, 2 tabs