BWR blowdown/emergency core cooling integral program
Description
The Program plan identifying the phased approach to testing has been completed and the first test phase is well underway. Test results to date show the expected lower peak cladding temperatures and slower system blowdown response for a BWR/6 LOCA simulation compared to the BWR/4. Counter-current flow limiting (CCFL) tests show that exact geometric replication was not necessary to simulate CCFL characteristics for a BWR prototype fuel bundle upper tie plate. Separate effects blowdown tests demonstrate the importance of flow length scaling in simulating break geometry for limiting the critical or blowdown flow rate. A new bundle thermal hydraulic method, MAYU04, has been completed. This method is shown to provide a substantial improvement in the prediction of bundle temperatures. The BD/ECC Program represents an important contribution to BWR safety research. Early results from the program have already provided a better understanding of the governing phenomena during hypothetical LOCA simulation tests. Future tests are expected to provide a basis for further improvements in BWR LOCA phenomena modeling
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- Thermal reactor safety. Vol. II
- Journal Page Range
- p. 621-632.
Conference
- Title
- Thermal reactor safety meeting.
- Dates
- 31 Jul - 5 Aug 1977.
- Place
- Sun Valley, ID, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10437536
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; BWR TYPE REACTORS; ECCS; HEAT TRANSFER; HYDRAULICS; PERFORMANCE TESTING
- Descriptors DEC
- ENERGY TRANSFER; REACTOR PROTECTION SYSTEMS; REACTORS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS