Open AccessSCDAP/RELAP5/MOD 3.1 Code Manual: Developmental assessment. Volume 5
Author(s) -
J.K. Hohorst,
E. C. Johnsen,
C.M. Allison
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/91932
Subject(s) - scram , boiler feedwater , nuclear engineering , coolant , transient (computer programming) , loss of coolant accident , control rod , pressurized water reactor , engineering , accident management , environmental science , turbine , mechanical engineering , computer science , operating system
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 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 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 code-to-data calculations performed using SCDAP/RELAP5/MOD3.1, as well as comparison calculations performed with earlier code versions. Results of full plant calculations which include Surry, TMI-2, and Browns Ferry are described. Results of a nodalization study, which accounted for both axial and radial nodalization of the core, are also reported