The Modeling and Evaluation of NSSS Control Systems of KSNP Using RETRAN-3D
- FNC Technology Co., SNU Research Park Innovation Center 516, San4-2, Bongchun-7 dong, Kwanak-Gu, Seoul (Korea, Republic of)
- Korea Electric Power Research Institute, Munji-Dong 103-16, Yusung-Gu, Taejun (Korea, Republic of)
The NSSS (Nuclear Steam Supply System) control systems perform automatic mitigation of transient conditions which can occur during power operation of nuclear power plant without operator actions. Thus appropriate modeling of NSSS control systems is required to analyze various transient conditions which can occur in nuclear power plant. In this paper, the NSSS control systems were modeled to analyze Non-LOCA transient conditions for Ulchin units 3 and 4, KSNP(Korea Standard Nuclear Power Plant) using RETRAN-3D. RETRAN-3D can analyze thermal hydraulic transients and is convenient to model control system through various control elements. The NSSS control systems for KSNP are composed of six parts. They, are, PPCS (Pressurizer Pressure Control System), PLCS (Pressurizer Level Control System), RRS (Reactor Regulating System), FWCS (Feedwater Control System), SBCS (Steam Bypass Control System and, RPCS (Reactor Power Cutback System). All control systems are connected each other systematically. The general RETRAN-3D analysis models were evaluated by analyzing the actual plant transient data for the turbine trip. And the performance analyses were performed to validate and evaluate prepared control systems. The performance analyses have several categories.They are small/large step power change, ramp power change and upset event. And each one of the performance evaluation categories is divided into several design bases events. The cases of performance analysis were chosen according to the performance evaluation categories. In the results of validation and evaluation, the important thermal hydraulic parameters were stabilized by the actuation of control systems without the reactor scram or the actuation of the plant safety systems, such as the safety injection system, auxiliary feedwater system and pressurizer/SG safety valves. It was evaluated that the NSSS control systems for KSNP prepared by RETRAN-3D were modeled and operated appropriately. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21160638
- 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; 4 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
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