Design base transient analysis using the real-time nuclear reactor simulator model

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:6304988

Tien, K K; Yakura, S J; Morin, J P; Gregory, M V

A real-time simulation model has been developed to describe the dynamic response of all major systems in a nuclear process reactor. The model consists of a detailed representation of all hydraulic components in the external coolant circulating loops consisting of piping, valves, pumps and heat exchangers. The reactor core is described by a three-dimensional neutron kinetics model with detailed representation of assembly coolant and moderator thermal hydraulics. The models have been developed to support a real-time training simulator, therefore, they reproduce system parameters characteristic of steady state normal operation with high precision. The system responses for postulated severe transients such as large pipe breaks, loss of pumping power, piping leaks, malfunctions in control rod insertion, and emergency injection of neutron absorber are calculated to be in good agreement with reference safety analyses. Restrictions were imposed by the requirement that the resulting code be able to run in real-time with sufficient spare time to allow interfacing with secondary systems and simulator hardware. Due to hardware set-up and real plant instrumentation, simplifications due to symmetry were not allowed. The resulting code represents a coarse-node engineering model in which the level of detail has been tailored to the available computing power of a present generation super-minicomputer. Results for several significant transients, as calculated by the real-time model, are compared both to actual plant data and to results generated by fine-mesh analysis codes.

• Research Organization: Savannah River Lab., Aiken, SC (USA); Singer Co., Fairfield, NJ (USA)
• DOE Contract Number: AC09-76SR00001
• OSTI ID: 6304988
• Report Number(s): DP-MS-86-219; CONF-870418-7; ON: DE87011241
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ANALOG SYSTEMS
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
FUNCTIONAL MODELS
HEAT TRANSFER
HYDRAULICS
LEAKS
MATHEMATICAL MODELS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR OPERATION
REACTOR SAFETY
REACTOR SIMULATORS
REAL TIME SYSTEMS
SAFETY
SIMULATION
SIMULATORS
THERMAL POWER PLANTS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS