Published August 1980 | Version v1
Report Restricted

Tensile studies of irradiated zirconium in a liquid cesium/cadmium environment

Creators

Description

The objective of this study was to evaluate the susceptibility of pure zirconium (crystal bar and sponge) to cesium/cadmium embrittlement as a function of fluence, strain rate, elemental composition, test temperature, and thermal mechanical history. Uniaxial tensile tests were conducted as a means of evaluating the embrittling response of the material. Test results were evaluated on the basis of the appearance of the loading curves and the details of the fracture surfaces. Embrittlement mechanisms are discussed in an attempt to correlate the experimental results with known deformation processes in irradiated materials. 10 figures, 10 tables

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.

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Additional details

Publishing Information

Imprint Pagination
39 p.
Report number
GEAP--25324

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12596467
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Descriptors DEI
CADMIUM; CESIUM; CORROSION; DIFFUSION BARRIERS; EMBRITTLEMENT; FRACTURES; FUEL ELEMENTS; FUEL-CLADDING INTERACTIONS; LINERS; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; STRAINS; SURFACES; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; ZIRCONIUM
Descriptors DEC
ALKALI METALS; CHEMICAL REACTIONS; ELEMENTS; FAILURES; MECHANICAL PROPERTIES; METALS; RADIATION EFFECTS; REACTOR COMPONENTS; TRANSITION ELEMENTS