Determining critical flow valve characteristics using extrapolation techniques
Description
This report presents the methodology and documentation of the calibration of the Loss-of-Fluid Test (LOFT) power-operated relief and safety relief valve (PORV + SRV) for the L9-3 anticipated transient without scram (ATWS) experiment. A multiposition globe valve was calibrated to produce scaled high-pressure flow rates using a low-pressure calibration facility and a simple RELAP5 critical flow model to extrapolate the calibration data to expected operating pressures. It was demonstrated that an accurate high-pressure, multiphase flow calibration can be performed without the necessity of actual high-pressure testing. This technique, when applied to large pressurized water reactor (LPWR) safety and relief valves, represents a potentially large savings in the capacity qualification procedure of full-scale pressure reduction valves
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI85009842.
Files
Additional details
Additional titles
- Augmented title (English)
- L9-3 ATWS experiment in LOFT
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- NUREG/CR--4046
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16078191
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ATWS; CALIBRATION; ERRORS; FLOW RATE; LOFT REACTOR; PERFORMANCE; R CODES; SIMULATION; VALVES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL EQUIPMENT; DESIGN BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EGG--2357.