Application of RELAP5/MOD1 for calculation of safety and relief valve discharge piping hydrodynamic loads. Final report. [PWR]
Technical Report
·
OSTI ID:6504402
A series of operability tests of spring-loaded safety valves was performed at Combustion Engineering in Windsor, CT as part of the PWR Safety and Relief Valve Test Program conducted by EPRI on behalf of PWR Utilities in response to the recommendations of NUREG-0578 and the requirements of the NRC. Experimental data from five of the safety valve tests are compared with RELAP5/MOD1 calculations to evaluate the capability of the code to determine the fluid-induced transient loads on downstream piping. Comparisons between data and calculations are given for transients with discharge of steam, water, and water loop seal followed by steam. RELAP5/MOD1 provides useful engineering estimates of the fluid-induced piping loads for all cases.
- Research Organization:
- Intermountain Technologies, Inc., Idaho Falls, ID (USA)
- OSTI ID:
- 6504402
- Report Number(s):
- EPRI-NP-2479; ON: DE83901474
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CALCULATIONS
CONTROL EQUIPMENT
DATA
DYNAMIC LOADS
EQUIPMENT
EXPERIMENTAL DATA
FLOW REGULATORS
FLUID MECHANICS
HYDRAULICS
HYDRODYNAMICS
INFORMATION
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTORS
RELIEF VALVES
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CALCULATIONS
CONTROL EQUIPMENT
DATA
DYNAMIC LOADS
EQUIPMENT
EXPERIMENTAL DATA
FLOW REGULATORS
FLUID MECHANICS
HYDRAULICS
HYDRODYNAMICS
INFORMATION
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTORS
RELIEF VALVES
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS