TRAC-PF1/MOD1 post-test calculations of the OECD LOFT Experiment LP-SB-3

Technical Report · Sun Apr 01 00:00:00 EST 1990

DOI:https://doi.org/10.2172/6888641· OSTI ID:6888641

Allen, E J; Neill, A P ^[1]

---

1. UKAEA Atomic Energy Establishment, Winfrith (UK)

Analysis of the small, cold leg break, OECD LOFT Experiment LP-SB-3 using the best-estimate computer code TRAC-PF1/MOD1 is presented. Descriptions of the LOFT facility and the LP-SB-3 experiment are given and development of the TRAC-PF1/MOD1 input model is detailed. The calculations performed in achieving the steady state conditions, from which the experiment was initiated, and the specification of experimental boundary conditions are outlined. Results of the TRAC-PF1/MOD1 calculation are found to be generally consistent with those reported, by members of the OECD LOFT Program Review Group, in the LP-SB-3 Comparison Report.'' Overall trends with respect to pressure histories, minimum primary system mass inventory and accumulator behaviour are reasonably well reproduced by TRAC-PF1/MOD1. 17 refs., 26 figs., 3 tabs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; UKAEA Atomic Energy Establishment, Winfrith (UK)
• Sponsoring Organization: USNRC
• OSTI ID: 6888641
• Report Number(s): NUREG/IA-0022; ON: TI90012844
• Resource Relation: Other Information: This report contains 2 microfiche supplements
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
LOFT REACTOR
LOSS OF COOLANT
REACTOR CORES
BOUNDARY CONDITIONS
COMPUTER CALCULATIONS
EXPERIMENTAL DATA
FLOW RATE
FUEL CANS
HEAT TRANSFER
HYDRAULICS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
STEADY-STATE CONDITIONS
T CODES
TEST FACILITIES
TRANSIENTS
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
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
990200 - Mathematics & Computers