RELAP5/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-2
Technical Report
·
OSTI ID:5403110
- Consejo de Seguridad Nuclear, Madrid (Spain)
This document presents the analysis of the OECD LOFT LP-SB-2 Experiment performed by the Consejo de Seguridad Nuclear of Spain working group making use of RELAP5/MOD2 in the frame of the Spanish LOFT Project. LB-SB-2 experiment studies the effect of a delayed pump trip in a small break LOCA scenario with a 3-inch equivalent diameter break in the hot leg of a commercial PWR.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Consejo de Seguridad Nuclear, Madrid (Spain)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 5403110
- Report Number(s):
- NUREG/IA-0087; ON: TI92014291
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-2
RELAP/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-1
RELAP/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-1
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:10146165
RELAP/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-1
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:10146249
RELAP/MOD2 post-test calculation of the OECD LOFT experiment LP-SB-1
Technical Report
·
Tue Mar 31 23:00:00 EST 1992
·
OSTI ID:5281633
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
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOPERATION
DEVELOPING COUNTRIES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EUROPE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PUMPS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SPAIN
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOPERATION
DEVELOPING COUNTRIES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EUROPE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PUMPS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SPAIN
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS