Influence of reactor vessel nodalization in the coupled code analysis of Asymmetric Main Feedwater Isolation
Creators
- 1. Faculty of Electrical Engineering and Computing, Zagreb Univ. (Croatia)
Description
Asymmetric Main Feedwater Isolation (AMFWI) transient in one Steam Generator (SG) for NPP Krsko using RELAP5 standalone code and coupled code RELAP5- QUABOX/CUBBOX (R5QC) was analyzed. In the RELAP5 standalone calculation, a point kinetics model was used, while in the coupled code a three-dimensional (3D) neutronics model of QUABOX with different RELAP5 nodalization schemes of reactor vessel was used. Both code versions use best-estimate thermal-hydraulic system code for all components in the plant and include realistic description of plant protection and control systems. Two different types of calculations were performed: with and without automatic control rod system available. The AMFWI transient causes the great asymmetry of the transferred heat in the SGs and subsequently the asymmetry of the power produced across the core due to different reactivity feedback resulting from the thermal-hydraulic channels assigned to different loops. The work presented in the paper is a part of validation of the 3D coupled code R5QC in the analysis of asymmetric transients.(author)
Files
35095337.pdf
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Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-6207-17-2
- Imprint Title
- Proceedings of the International Conference Nuclear Energy in Central Europe 2001
- Imprint Pagination
- 97.2 Megabytes
- Journal Page Range
- [8 p.]
- Report number
- INIS-SI--04-001
Conference
- Title
- International Conference Nuclear Energy in Central Europe 2001
- Dates
- 10-13 Sep 2001
- Place
- Portoroz (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 35095337
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; FEEDWATER; KRSKO REACTOR; REACTOR VESSELS; SIMULATION; STEAM GENERATORS; THERMAL ANALYSIS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; VALIDATION
- Descriptors DEC
- BOILERS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MECHANICS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs., 1 tab., 6 figs. Imprint:702 refs., 125 tabs., 526 figs.