Published October 1980
| Version v1
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Study of small breaks and natural circulation in BWRs
Description
A study of small breaks and natural circulation in Boiling Water Reactors was performed to qualitatively assess the sequence and consequences of BWR small break situations. In addition to reviewing the small break scenario with single failures, the effect of multiple failures was reviewed to assess the amount of margin present. A steady-state thermal-hydraulic computer code was written to calculate reactor core conditions for small breaks and isolation events. A sample analysis of natural circulation in a BWR was calculated and presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
Files
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 125 p.
- Report number
- EPRI-NP--1564
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12588173
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT; AFTER-HEAT REMOVAL; BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; NATURAL CONVECTION; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS