LOFT natural circulation test analysis for 30% reactor power and high flow rate conditions. [PWR]

Technical Report · Wed Mar 07 23:00:00 EST 1979

OSTI ID:6269985

Fausz, N F

The results are presented for the LOFT natural circulation test analyses for conditions of nominal high loop flow rate and 30% of nominal full power. The test cases included a loss of commercial off-site power and several cases of loss of power to the primary coolant pumps with subsequent flywheel coastdown. The cases of loss of power to the primary coolant pumps were analyzed using a variety of reactor trips and one case in which no reactor trip occurred. In addition, the transients resulting from a loss of power to the primary coolant pumps were anlayzed using various degrees of increased natural circulation flow resistance.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6269985
• Report Number(s): LTR-111-120; RE-A-78-286
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
CONVECTION
DEPARTURE NUCLEATE BOILING
ENERGY TRANSFER
HEAT FLUX
HEAT TRANSFER
LOFT REACTOR
LOSS OF FLOW
NATURAL CONVECTION
NUCLEATE BOILING
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS