GESTR: a model for the prediction of GE BWR fuel rod thermal/mechanical performance
Description
The document provides a description of GESTR, a model for the prediction of GE BWR fuel rod thermal/mechanical performance. The GESTR model incorporates the effects of fuel/cladding thermal expansion, fuel/cladding creep and fuel irradiation swelling, densification, relocation, and fission gas release as they affect pellet-cladding thermal conductance, fuel rod internal pressure, and pellet/cladding mechanical interaction. This document provides a description of the GESTR individual model elements in addition to qualification of the integral model by comparison of GESTR predictions to experimental fuel rod deformation, pellet-cladding thermal conductance, fission gas release, and fuel rod internal pressure data
Availability note (English)
MF available from INIS under the Report Number; General Electric Co., San Jose, CA.
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Additional details
Publishing Information
- Imprint Pagination
- 58 p.
- Report number
- NEDO--23785
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9418658
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; FUEL RODS; G CODES; MATHEMATICAL MODELS; PERFORMANCE
- Descriptors DEC
- FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS