Published 1977
| Version v1
Book
Fuel operating experience in Westinghouse PWRs
Description
Westinghouse fuel experience from a data base of 29 plants with Zircaloy fuel clad demonstrates a continued high reliability. On-site surveillance programs indicate that previous defect mechanism such as clad hydriding due to moisture, fuel densification, clad flattening and clad defects following a rapid initial startup after refueling have been virtually eliminated. The class of potential defect mechanisms which have not compromised fuel performance (fuel rod bow, pellet-to-clad interaction at high power operation, corrosion and fretting) is undergoing extensive evaluation to verify the adequacy of the current designs and to develop design improvements. 6 refs
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- Chicago, IL
- Imprint Title
- Water reactor fuel performance, ans topical meeting, 1977
- Journal Page Range
- p. 60-70.
Conference
- Title
- ANS topical meeting on water reactor fuel performance.
- Dates
- 9 - 11 May 1981.
- Place
- St Charles, IL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12642262
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; DEFECTS; DEFORMATION; FUEL ELEMENTS; FUEL-CLADDING INTERACTIONS; PERFORMANCE; PWR TYPE REACTORS
- Descriptors DEC
- CHEMICAL REACTIONS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS