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Title: SCDAP/RELAP5/MOD 3.1 code manual: Damage progression model theory. Volume 2

SCDAP/RELAP5/MOD 3.1 code manual: Damage progression model theory. Volume 2 The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, 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 as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume contains detailed descriptions of the severe accident models and correlations. It provides the user with the underlying assumptions and simplifications used to generate and implement the basic equations into the code, so an intelligent assessment of the applicability and accuracy of the resulting calculation can be made.
Authors: ; ;
Publication Date:
OSTI Identifier:100325
Report Number(s):NUREG/CR--6150-Vol.2; EGG--2720-Vol.2
ON: TI95015036; TRN: 95:019256
DOE Contract Number:AC07-94ID13223
Resource Type:Technical Report
Data Type:
Resource Relation:Other Information: PBD: Jun 1995
Research Org:Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Sponsoring Org:Nuclear Regulatory Commission, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; BWR TYPE REACTORS; REACTOR ACCIDENTS; PWR TYPE REACTORS; COMPUTERIZED SIMULATION; S CODES; R CODES; TRANSIENTS; OUTAGES; LOSS OF FLOW; REACTOR COOLING SYSTEMS; HEAT TRANSFER; HYDRAULICS; REACTOR SAFETY