Development of the RETRAN-3D input model for Kori unit 1 transient analyzer
Description
Korea Atomic Energy Institute (KAERI) has developed Visual System Analyzer (ViSA) based on MARS and RETRAN-3D for a Loss of Coolant Accident (LOCA) and a non-LOCA, respectively. To analyze non-LOCA transient and Small Break LOCA where break size is less than 3 inches diameter, it is necessary to develop the RETRAN-3D input model for a specific plant. Recognizing these requirements, we have developed the RETRAN-3D input model for Kori Unit 1. Moreover, detailed calculation notes for each input parameter have been developed using Math-CAD software and attached to this report as appendices. The geometric input data of plant is more focused on Nuclear Steam Supply System (NSSS), whereas other Balance of Plant (BOP) system is treated as a boundary condition. The control system input has been developed including the interlock signal as well as protection, control and safety system. Therefore, it is possible to simulate an accident analysis and a general plant operation, including up and down power operations. To confirm the validity of input data, we have performed the calculations for various transient conditions as well as the calculations for a steady state at 100 % power operation condition. Finally we found that the developed input deck could be used as a base input deck for the RETRAN-3D transient analyzer of Kori Unit 1, because the calculation results were well consistent with those by other best-estimate calculations
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
36095411.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 300 p.
- Report number
- KAERI/TR--2798/2004
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36095411
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; CONTROL SYSTEMS; KORI-1 REACTOR; LOSS OF COOLANT; M CODES; R CODES; STEAM SYSTEMS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 28 figs, 3 tabs