Burnup limits in PWR and in BWR fuel
- 1. Stoller (S.M.) Corp., Pleasantville, NY (USA)
Description
The design of future cores will be based on burnup limits that are currently expanding. The performance parameters that have limited the burnup potential for current fuels in BWRs and in PWRs will be identified. Any changes that are justified through data from lead test assemblies (LTAs) or other improvements will be reported. Performance issues such as Zircaloy growth, pellet-cladding interaction (PCI), corrosion, Zircaloy ductility, fuel rod internal pressure will be discussed relative to potential limits. Some of these are limiting because of fuel rod integrity and others because of licensing or commercial considerations. Potential limits that arise from nuclear design considerations will also be described for general cases where peaking or other limits may be reached at lower values than those due to mechanical integrity, for example. Where representative data are available for classes of BWRs and PWRs, operating limits will be projected for use by those utilities with plants in these categories. (author). 10 figs
Additional details
Publishing Information
- Imprint Title
- Fuel performance at high burnup for water reactors
- Imprint Pagination
- 216 p.
- Journal Page Range
- p. 208-213.
- Report number
- IWGFPT--36
Conference
- Title
- Technical committee meeting on fuel performance at high burnup for water reactors.
- Dates
- 5-8 Jun 1990.
- Place
- Studsvik (Sweden).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 22091324
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; CORROSION; DUCTILITY; ELONGATION; FUEL ASSEMBLIES; FUEL INTEGRITY; FUEL-CLADDING INTERACTIONS; LIMITING VALUES; PRESSURE GRADIENTS; PWR TYPE REACTORS; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; DEFORMATION; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS