GAS-PASS/H: A Simulation Code for Gas Reactor Plant Systems

Conference · Thu Jul 01 00:00:00 EDT 2004

OSTI ID:21160787

Mertyurek, U ^[1]; Vilim, R B; Cahalan, J E ^[2]

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1. Texas A and M University, Department of Nuclear Engineering, College station, TX 77843-3133 (United States)
2. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

A simulation code has been developed for use in safety analysis and control studies of Generation-IV gas reactor concepts. Computational efficiency is achieved by use of spatially lumped conservation equations for modeling system components. Modularized programming of these components provides the capability to configure a plant system through the user input and permits modeling of both direct and indirect cycles. Performance curves are used for modeling turbomachinery while point kinetic equations are employed for the neutronics modeling. An unprotected loss of load transient is simulated for a direct cycle gas cooled fast reactor and plant response is described. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160787
• Resource Relation: Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 7 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
• Country of Publication: United States
• Language: English

Related Subjects

99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
42 ENGINEERING
CONTROL
DIAGRAMS
EFFICIENCY
FAST REACTORS
KINETIC EQUATIONS
LICENSES
PERFORMANCE
PROGRAMMING
SAFETY ANALYSIS
SIMULATION
TURBOMACHINERY