Study on diagnostic plant analyzer method for support of emergency operation
- 1. Institute of Atomic Energy, Kyoto Univ., Gokasho, Uji, Kyoto
Description
Methods of time-critical diagnostic plant analyzer are investigated which would serve as support to emergency operation of nuclear power plant. A faster-than-real-time simulator code TOKRAC is developed for analyzing PWR primary loop thermo-hydraulics of small-break LOCA and it is applied for a numerical experiment of initial phase of TMI-2 accident. TOKRAC resulted in a good agreement with a RELAP4/MOD6 calculation and the plant record with as fast as can one-tenth of real time. A real-time estimator of SG heat transfer rate based on Kalman filter is proposed and its applicability is verified using LOFT ATWS experimental data. With regards to how to integrate those methods into the software system in operation support center, a new concept of module-based simulation system is proposed which aims at offering a flexible and human-cognitive oriented environment for various analytical tool development
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- ISBN
- 0-89448-121-5
- Imprint Title
- Proceedings of the international ANS/ENS topical meeting on thermal reactor safety
- Journal Page Range
- p. XII3.1-XII3.8.
Conference
- Title
- International ANS/ENS topical meeting on thermal reactor safety.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18080563
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; EMERGENCY PLANS; ENGINEERING; HEAT TRANSFER; HUMAN FACTORS; HYDRAULICS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; R CODES; REACTOR OPERATION; REACTOR SAFETY; REAL TIME SYSTEMS; T CODES; THERMODYNAMICS; THREE MILE ISLAND-2 REACTOR; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS