Published 2001 | Version v1
Miscellaneous Open

Influence of reactor vessel nodalization in the coupled code analysis of Asymmetric Main Feedwater Isolation

  • 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)

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Part of:
Proceedings of the International Conference Nuclear Energy in Central Europe 2001

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)

Optional Information

Notes
10 refs., 1 tab., 6 figs. Imprint:702 refs., 125 tabs., 526 figs.