GRSAC Users Manual

Technical Report · Mon Feb 01 00:00:00 EST 1999

DOI:https://doi.org/10.2172/5612· OSTI ID:5612

Ball, S J; Nypaver, D J

An interactive workstation-based simulation code (GRSAC) for studying postulated severe accidents in gas-cooled reactors has been developed to accommodate user-generated input with ''smart front-end'' checking. Code features includes on- and off-line plotting, on-line help and documentation, and an automated sensitivity study option. The code and its predecessors have been validated using comparisons with a variety of experimental data and similar codes. GRSAC model features include a three-dimensional representation of the core thermal hydraulics, and optional ATWS (anticipated transients without scram) capabilities. The user manual includes a detailed description of the code features, and includes four case studies which guide the user through four different examples of the major uses of GRSAC: an accident case; an initial conditions setup and run; a sensitivity study; and the setup of a new reactor model.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 5612
• Report Number(s): ORNL/TM-13697; TRN: US0101679
• Resource Relation: Other Information: PBD: 1 Feb 1999
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
G CODES
REACTOR ACCIDENTS
DOCUMENTATION
HYDRAULICS
MANUALS
SCRAM
SENSITIVITY ANALYSIS
COMPUTERIZED SIMULATION
GAS COOLED REACTORS
REACTOR CORES
ATWS
GAS-COOLED REACTORS
ACCIDENT SCENARIOS