Base input for LOFT RELAP5 calculations

Technical Report · Tue Jul 01 00:00:00 EDT 1980

OSTI ID:5630381

Kee, E J; Schally, P J; Winters, L

This report describes the input data set, based on the latest information of the LOFT system, to be used with the RELAP5/MODO digital computer code. The data set is for simulations of the transient thermal hydraulic behavior occurring in the primary and secondary coolant systems and relaxed subsystems such as the pressurizer and ECC when the LOFT integral test facility undergoes a LOCE or operational transient. Data are included for the intact loop, reactor vessel, broken loop, pressurizer, steam generator secondary, and ECC system.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5630381
• Report Number(s): EGG-LOFT-5199; ON: TI85014382
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
COMPUTER CODES
LOSS OF COOLANT
PWR TYPE REACTORS
R CODES
SIMULATION
ACCIDENTS
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled