Published 1977 | Version v1
Book Metadata-only

High-temperature deformation and rupture behavior of internally pressurized Zircaloy-4 cladding in vacuum and steam environments

Creators

  • 1. Argonne National Lab., IL

Description

The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 13500C

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL
Imprint Title
Thermal reactor safety. Vol. III
Journal Page Range
p. 60-85.

Conference

Title
Thermal reactor safety meeting.
Dates
31 Jul - 5 Aug 1977.
Place
Sun Valley, ID, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10437274
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFORMATION; FUEL CANS; GRAIN GROWTH; LOSS OF COOLANT; MICROSTRUCTURE; STEAM; STRAINS; VERY HIGH TEMPERATURE; WATER COOLED REACTORS; ZIRCALOY 4
Descriptors DEC
ACCIDENTS; ALLOYS; CRYSTAL STRUCTURE; REACTOR ACCIDENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS