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]
Abstract
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.
- Publication Date:
- Research Org.:
- Idaho National Engineering Lab., Idaho Falls (USA)
- OSTI Identifier:
- 7334741
- Report Number(s):
- TID-27136/2
TRN: 77-000165
- DOE Contract Number:
- E(10-1)-1375
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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
Citation Formats
. 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]. United States: N. p., 1976.
Web.
. 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]. United States.
. 1976.
"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]". United States.
@article{osti_7334741,
title = {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]},
author = {},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/7334741},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jun 01 00:00:00 EDT 1976},
month = {Tue Jun 01 00:00:00 EDT 1976}
}
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