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DOI 10.2172/100083
Title RELAP/MOD3 code manual: User`s guidelines. Volume 5, Revision 1
Creator/Author Fletcher, C.D. ; Schultz, R.R. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)]
Publication Date1995 Aug 01
OSTI IdentifierOSTI ID: 100083; Legacy ID: TI95017604
Report Number(s)NUREG/CR--5535-Vol.5-Rev.1; INEL--95/0174-Vol.5-Rev.1
DOE Contract NumberAC07-76ID01570
DOI10.2172/100083
Other Number(s)Other: ON: TI95017604
Resource TypeTechnical Report
Resource RelationOther Information: PBD: Aug 1995
Research OrgNuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Sponsoring OrgNuclear Regulatory Commission, Washington, DC (United States)
Subject22 NUCLEAR REACTOR TECHNOLOGY ;21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LOSS OF COOLANT; R CODES; PWR TYPE REACTORS; BWR TYPE REACTORS; REACTOR COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; HEAT TRANSFER; HYDRAULICS; REACTOR SAFETY
Description/AbstractThe RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits simulating a variety of thermal hydraulic systems. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater systems. Volume V contains guidelines that have solved over the past several years through the use of the RELAP5 code.
Country of PublicationUnited States
LanguageEnglish
FormatMedium: P; Size: 200 p.
Availability INIS; OSTI as TI95017604
System Entry Date2008 Feb 04
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