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

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

OSTI ID:7334741

A discussion is presented of the use of the RELAP4/MOD5 computer program in simulating the thermal-hydraulic behavior of light-water reactor systems when subjected to postulated transients such as a LOCA, pump failure, or nuclear excursion. The volume is divided into main sections which cover: (1) program description, (2) input data, (3) problem initialization, (4) user guidelines, (5) output discussion, (6) source program description, (7) implementation requirements, (8) data files, (9) description of PLOTR4M, (10) description of STH20, (11) summary flowchart, (12) sample problems, (13) problem definition, and (14) problem input.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• OSTI ID: 7334741
• Report Number(s): TID-27136/2; TRN: 77-000165
• 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