Published August 1976
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Zircaloy fuel cladding collapse test plan
Description
This test plan outlines the experimental philosophy and procedures for investigating the deformation behavior of Zircaloy fuel cladding under normal and near-normal reactor operating conditions. Such conditions impose compressive hoop and axial stresses on the cladding at temperatures that encompass the time-dependent or creep-strain regime. The purpose of the outlined study is to understand the deformation behavior of cladding under in- and out-of-reactor conditions so that mechanical properties correlations may be developed
Availability note (English)
MF available from INIS under the Report Number.Files
8290675.pdf
Files
(1.1 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 52 p.
- Report number
- ORNL/NUREG/TM--45
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8290675
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; DEFORMATION; FUEL CANS; PWR TYPE REACTORS; STRAINS; STRESSES; TESTING; ZIRCALOY
- Descriptors DEC
- ALLOYS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Available from NTIS. $4.50.