Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
Technical Report
·
OSTI ID:7368459
- Union Electrica, SA, Madrid (Spain)
This document presents the comparison between the simulation results and the plant measurements of a real event that took place in JOSE CABRERA nuclear power plant in August 30th, 1984. The event was originated by the total, continuous and inadverted opening of the pressurizer spray valve PCV-400A. JOSE CABRERA power plant is a single loop Westinghouse PWR belonging to UNION ELECTRICA FENOSA, S.A. (UNION FENOSA), an Spanish utility which participates in the International Code Assessment and Applications Program (ICAP) as a member of UNIDAD ELECTRICA, S.A. (UNESA). This is the second of its two contributions to the Program: the first one was an application case and this is an assessment one. The simulation has been performed using the RELAP5/MOD2 cycle 36.04 code, running on a CDC CYBER 180/830 computer under NOS 2.5 operating system. The main phenomena have been calculated correctly and some conclusions about the 3D characteristics of the condensation due to the spray and its simulation with a 1D tool have been got.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research; Union Electrica, SA, Madrid (Spain)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- OSTI ID:
- 7368459
- Report Number(s):
- NUREG/IA-0124; ON: TI93016346
- Country of Publication:
- United States
- Language:
- English
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Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera Nuclear Station
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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
AGREEMENTS
COMPUTER CODES
CONTROL EQUIPMENT
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURES
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL AGREEMENTS
MASS TRANSFER
MECHANICS
NATURAL CONVECTION
POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
R CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL REACTORS
TRANSIENTS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZORITA-1 REACTOR
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
AGREEMENTS
COMPUTER CODES
CONTROL EQUIPMENT
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURES
FLOW REGULATORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL AGREEMENTS
MASS TRANSFER
MECHANICS
NATURAL CONVECTION
POWER REACTORS
PRESSURIZERS
PWR TYPE REACTORS
R CODES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
THERMAL REACTORS
TRANSIENTS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZORITA-1 REACTOR