Published 1974
| Version v1
Report
Westinghouse nuclear fuel operating experience
Creators
Description
Operating experience with Westinghouse Zircaloy-clad nuclear fuel is reviewed. Problems related to moisture, fuel densification, rod flattening, fretting, and rod bowing are discussed
Additional details
Publishing Information
- Imprint Title
- 1974 electric utility engineering conference. Volume II
- Imprint Pagination
- vp, Paper 13 p.
- Report number
- CONF-740341--P2
Conference
- Title
- Electric utility engineering conference.
- Dates
- 3 Mar 1974.
- Place
- Pittsburgh, Pennsylvania, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7256142
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DEFORMATION; FUEL DENSIFICATION; FUEL ELEMENTS; PERFORMANCE; PWR TYPE REACTORS; REVIEWS; ZIRCALOY
- Descriptors DEC
- ALLOYS; DOCUMENT TYPES; REACTOR COMPONENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Imprint:Westinghouse Electric Corp., P.O. Box 355, Pittsburgh, Pa. 15230.