Published August 1971
| Version v1
Journal article
Effect of fuel rod failure on emergency core cooling system design for boiling water reactors
Description
The experimental results of fuel rod failure on the heat transfer effectiveness of spray cooling a Zircaloy-clad simulated BWR fuel bundle were evaluated from the design engineer viewpoint to determine the adequacy of the emergency core cooling system (ECCS) design. The overall results of the full-size 49-rod Zircaloy-clad internally pressurized bundle indicate that the ballooning and perforation associated with cladding failure did not significantly change the heat transfer effectiveness (i.e., peak cladding temperatures) of the ECCS spray cooling mode. Furthermore, the distortion was local in nature so the flow area reduction would not affect the ability of the ECCS flooding mode to accomplish the design objectives.
Additional details
Identifiers
- DOI
- 10.13182/nt71-a30851;
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 11
- Journal Issue
- 4
- Series
- Nucl. Technol.
- Journal Page Range
- 544-550
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 3016049
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- No Abstract
- Descriptors DEI
- BOILING WATER REACTORS; DEFORMATION; ECCS; FAILURES; FUEL CANS; FUEL RODS; HEAT TRANSFER; PERFORMANCE; REACTOR SAFETY; SPRAY; ZIRCALOY
- Descriptors DEC
- FUEL ELEMENTS; REACTOR MATERIALS; RODS; SPUTTERING; WATER COOLED REACTORS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent