Study of time-critical diagnostic method for emergency operation of nuclear power plant
- 1. Mitsubishi Atomic Power Industry Co., Ltd., Kyoto
Description
In order to support the emergency operation of nuclear power plant, the method of time-critical diagnostic plant analyzer has been investigated. The conception of the emergency operation support center is proposed and two types of plant analyzer may be installed in this center. One analyzer is a real-time tracking simulation code using the observed signals and another is a fast trend-prediction code. A real-time tracking code, TOKRAC, has been developed for analyzing the PWR primary loop thermo-hydraulics at SBLOCA, and the applicability of this code was examined by the numerical experiments for the initial phase transient of both TMI-2 accident and 6% coldleg SBLOCA of a Westinghouse-type PWR plant. The results showed that fairly good tracking was carried out by TOKRAC. The CPU time of TOKRAC was about 12-14 percent of real-time
Additional details
Publishing Information
- Publisher
- University of Tennessee.
- Imprint Place
- Knoxville, TN (USA)
- Imprint Title
- Proceedings of power plant dynamics, control and testing symposium
- Journal Page Range
- p. 67.01-67.25.
Conference
- Title
- 6. power plant dynamics, control and testing symposium.
- Dates
- 14-16 Apr 1986.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18014608
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; COMPUTERIZED SIMULATION; DIAGNOSTIC TECHNIQUES; DIGITAL FILTERS; FLOW RATE; G CODES; HEAT TRANSFER; HYDRAULICS; LEAKS; LOFT REACTOR; LOSS OF COOLANT; NUCLEAR POWER PLANTS; ON-LINE CONTROL SYSTEMS; PERT METHOD; PRIMARY COOLANT CIRCUITS; REACTOR SIMULATORS; REAL TIME SYSTEMS; RUPTURES; SIGNALS; STEAM GENERATORS; T CODES; TELEVISION; THERMODYNAMICS; THREE MILE ISLAND-2 REACTOR; TIME DEPENDENCE; TRANSIENTS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; BOILERS; COMPUTER CODES; CONTROL SYSTEMS; COOLING SYSTEMS; DESIGN BASIS ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FAILURES; FUNCTIONAL MODELS; NUCLEAR FACILITIES; ON-LINE SYSTEMS; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SIMULATORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS