Two-phase pump performance program preliminary test plan. Key phase report
Description
A major concern in the design of power reactors is that sufficient cooling capability be provided to keep fuel element clad temperatures below specified values, even for a postulated break in principal coolant loop components such as the main recirculation loop pipe. Therefore, it is necessary to be able to predict reactor system performance in such a loss-of-coolant accident (LOCA) and to evaluate accident preventing and/or mitigating steps in the design of he system. As a part of the continuing effort for improving and advancing safety technology, the C-E/EPRI Two-Phase Pump Performance Project is designed to provide basic data on the reactor coolant recirculation pump performance under two-phase flow LOCA conditions. Present pump analytical models generally in use for LOCA calculations employ homologous flow relationships to derive head and torque behavior in the two-phase flow regimes, and an empirical head degradation factor based on limited experimental information is generally used. This project is aimed at providing sufficient steady-state and transient two-phase empirical data to improve the presently used analytical modeling. Pump overspeed characteristics will also be examined
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR and BWR
Publishing Information
- Imprint Pagination
- 146 p.
- Report number
- EPRI-NP--128
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8343903
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; HYDRAULICS; LOSS OF COOLANT; PERFORMANCE TESTING; PRIMARY COOLANT CIRCUITS; PUMPS; PWR TYPE REACTORS; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS