Open AccessSCDAP/RELAP5/MOD 3.1 code manual: Interface theory. Volume 1
Author(s) -
C.M. Allison,
G.A. Berna
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/95198
Subject(s) - scram , boiler feedwater , nuclear engineering , code (set theory) , transient (computer programming) , coolant , control rod , loss of coolant accident , computer science , source code , pressurized water reactor , interface (matter) , simulation , engineering , mechanical engineering , turbine , parallel computing , programming language , set (abstract data type) , bubble , maximum bubble pressure method
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, core, fission product 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 off-site 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 describes the organization and manner of the interface between severe accident models which are resident in the SCDAP portion of the code and hydrodynamic models which are resident in the RELAP5 portion of the code. A description of the organization and structure of SCDAP/RELAP5 is presented. Additional information is provided regarding the manner in which models in one portion of the code impact other parts of the code, and models which are dependent on and derive information from other subcodes