LOFT steam generator simulator and pump simulator performance during LOFT isothermal test Series L1
Technical Report
·
OSTI ID:5580772
The Loss-of-Fluid Test (LOFT) facility simulates the thermal-hydraulic conditions typical of a large pressurized water reactor (PWR) and is designed to provide data from loss-of-coolant experiments (LOCE). Isothermal Test Series L1 was performed in LOFT with a steam generator simulator and pump simulator in the broken loop hot leg for Tests L1-2 through L1-5 and in the broken loop cold leg for Test L1-1. This report examines the performance of the steam generator simulator and pump simulator during LOFT isothermal Test Series L1 and is an extension of the work reported in LTR 20-14. The evaluation of the component simulators was performed using the RELAP4/MOD5 computer code, and using the results from this evaluation, an assessment of RELAP4/MOD5 was also performed.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5580772
- Report Number(s):
- EGG/LTR-20-101; ON: DE85015873
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ANALOG SYSTEMS
BOILERS
COMPUTER CODES
FLUID MECHANICS
FUNCTIONAL MODELS
HYDRAULICS
LOFT REACTOR
MECHANICS
PRESSURE DROP
PUMPS
PWR TYPE REACTORS
R CODES
REACTORS
RESEARCH AND TEST REACTORS
SIMULATORS
STEAM GENERATORS
TANK TYPE REACTORS
TEST REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ANALOG SYSTEMS
BOILERS
COMPUTER CODES
FLUID MECHANICS
FUNCTIONAL MODELS
HYDRAULICS
LOFT REACTOR
MECHANICS
PRESSURE DROP
PUMPS
PWR TYPE REACTORS
R CODES
REACTORS
RESEARCH AND TEST REACTORS
SIMULATORS
STEAM GENERATORS
TANK TYPE REACTORS
TEST REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS