The RELAP5/MOD3 computer code
Conference
·
OSTI ID:6980462
RELAP5/MOD3 is a pressurized water reactor (PWR) system analysis code being developed jointly by the U.S. Nuclear Regulatory Commission (USNRC) and a consortium consisting of several of the countries and domestic organizations that are members of the International Code Assessment and Applications Program (ICAP). The mission of the RELAP5/MOD3 code development program is to develop a code version suitable for the analysis of all transients and postulated accidents in PWR systems including both large and small break loss of coolant accidents (LOCA's) as well as the full range of operational transients. Although the emphasis of the RELAP5/MOD3 development is on large break LOCA, improvements to existing code models, based on the results of assessments against small break LOCA and operational transient test data, are also being made. This paper discusses the new code models as well as improvements to existing models. 13 refs., 6 figs., 1 tab.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6980462
- Report Number(s):
- EGG-M-89393; CONF-8909248--2; ON: DE90010947
- Country of Publication:
- United States
- Language:
- English
Similar Records
Plans and status of RELAP5/MOD3
RELAP5/MOD3 AP600 problems
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Conference
·
Sat Dec 31 23:00:00 EST 1988
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OSTI ID:7038326
RELAP5/MOD3 AP600 problems
Conference
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Sun Aug 01 00:00:00 EDT 1993
·
OSTI ID:10181594
RELAP5/MOD3 Code Manual
Technical Report
·
Tue Dec 31 23:00:00 EST 1991
·
OSTI ID:5559769
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW BLOCKAGE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LAYERS
LOSS OF COOLANT
MECHANICS
MODIFICATIONS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
VAPOR CONDENSATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLOW BLOCKAGE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LAYERS
LOSS OF COOLANT
MECHANICS
MODIFICATIONS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TRANSIENTS
VAPOR CONDENSATION
WATER COOLED REACTORS
WATER MODERATED REACTORS