RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume I. RELAP4/MOD5 description. [BWR; PWR]

Technical Report · Tue Jun 01 00:00:00 EDT 1976

OSTI ID:7252062

Bruch, C G ^[1]

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1. ed.

A detailed description is presented of the RELAP4/MOD5 computer program. RELAP4 is written in FORTRAN IV for analysis of nuclear reactors and related systems. It is primarily applied in the study of system transient response to postulated perturbations such as coolant loop rupture, circulation pump failure, power excursions, etc. The program was written to be used for water cooled (PWR and BWR) reactors and can be used for scale models such as LOFT and SEMISCALE. Additional versatility extends its usefulness to related applications, such as ice condenser and containment subcompartment analysis. Specific options are available for reflood (FLOOD) analysis and for the Evaluation Model.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• OSTI ID: 7252062
• Report Number(s): TID-27136/1; TRN: 77-000164
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
COMPUTER CODES
R CODES
HYDRAULICS
PWR TYPE REACTORS
BLOWDOWN
COMPUTER CALCULATIONS
EXCURSIONS
MANUALS
MATHEMATICAL MODELS
REACTOR COOLING SYSTEMS
TRANSIENTS
ACCIDENTS
COOLING SYSTEMS
DOCUMENT TYPES
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled