Published 1986
| Version v1
Journal article
Prediction of fuel cladding strain during post-boiling transition operation
Description
To obtain a basic understanding of the integrity of fuel cladding at elevated temperatures characteristic of operation beyond boiling transition in boiling water reactors, a new description of the transient deformation behavior for unirradiated Zircaloy-2 cladding was developed, using the Larson-Miller parameter (LMP) life-fraction approach. It is possible that the LMP life-fraction approach may give useful information to determine the criteria necessary to minimize fuel cladding damage during the post-boiling transition operation
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 52
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 520-521
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 15-20 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18065820
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-ZR98SN-2; BOILING; BWR TYPE REACTORS; DEFORMATION; FUEL CANS; FUEL INTEGRITY; PRESSURE DEPENDENCE; REACTOR SAFETY; STRAINS; STRESSES; TEMPERATURE DEPENDENCE; TIME DEPENDENCE; TRANSIENTS
- Descriptors DEC
- ALLOYS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; IRON ADDITIONS; NICKEL ADDITIONS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-860610--.