BWR Refill-Reflood Program: Task 4.3 - Single Heated Bundle. Final report
Description
Separate effects and system response tests conducted in the Single Heated Bundle (SHB) facility have produced data for evaluating: (a) low flow core spray heat transfer; (b) bundle bottom reflood heat transfer; (c) channel to bypass heat transfer; and (d) BWR refill-reflood controlling phenomena. These data support model development and qualification. Transient Loss of Coolant Accident (LOCA) experiments conducted in the SHB test facility have demonstrated that an adiabatic bundle system, using steam injection to simulate vaporization, simulates the thermal-hydraulic system response of a heated bundle system. These tests which were conducted by subjecting the adiabatic bundle and then an electrically heated bundle to the same LOCA transients, confirm the application of the adiabatic steam injection technique to a large-scale test facility
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01 - GPO $5.50 as DE83901796.
Files
Additional details
Publishing Information
- Imprint Pagination
- 80 p.
- Report number
- NUREG/CR--2001
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14783410
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; FUEL ASSEMBLIES; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; REACTOR SAFETY; SPATIAL DISTRIBUTION; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EPRI-NP--2372; GEAP--24936.