Published May 1976
| Version v1
Report
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ATWS analyses. Analysis of anticipated transients without reactor scram in Combustion Engineering NSSS's
Description
Results are presented of analyses of the transient thermal-hydraulic conditions and radiological release consequences which would occur in power plants which employ a Combustion Engineering Nuclear Steam Supply System during Anticipated Transients Without Scram due to a lack of insertion of the Control Element Assemblies upon signals for automatic or manual reactor shutdown. The transients analyzed include all events which meet the criterion to be considered as anticipated at least once in the plant lifetime with automatic reactor shutdown
Availability note (English)
MF available from INIS under the Report Number.
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- v p.
- Report number
- CENPD--158(Rev.1)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8290168
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ATWS; FISSION PRODUCT RELEASE; HYDRAULICS; PRESSURE GRADIENTS; PWR TYPE REACTORS; THERMODYNAMICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; DESIGN BASIS ACCIDENTS; REACTOR ACCIDENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Combustion Engineering, Inc., Windsor, CT.