SCDAP/RELAP5/MOD 3.1 code manual: Damage progression model theory. Volume 2
Author(s) -
K. L. Davis,
C.M. Allison,
G.A. Berna
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/100325
Subject(s) - scram , boiler feedwater , nuclear engineering , transient (computer programming) , coolant , loss of coolant accident , pressurizer , pressurized water reactor , control rod , code (set theory) , reliability engineering , computer science , engineering , mechanical engineering , turbine , operating system , set (abstract data type) , programming language
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
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