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.