Published November 2003 | Version v1
Miscellaneous Open

Final results of the sixth three-dimensional AER dynamic Benchmark problem calculation. Solution of problem with DYN3D and RELAP5-3D codes

  • 1. Nuclear Research Institute Rez plc, 250 68 Rez (Czech Republic)

Description

The paper gives a brief survey of the 6th three-dimensional AER dynamic benchmark calculation results received with the codes DYN3D and RELAP5-3D at NRI Rez. This benchmark was defined at the 10th AER Symposium. Its initiating event is a double ended break in the steam line of steam generator No. 1 in a WWER-440/213 plant at the end of the first fuel cycle and in hot full power conditions. Stationary and burnup calculations as well as tuning of initial state before the transient were performed with the code DYN3D. Transient calculations were made with the system code RELAP5-3D. The KASSETA library was used for the generation of reactor core neutronic parameters. The detailed six loops model of NPP Dukovany was adopted for the 6th AER dynamic benchmark purposes. The RELAP5-3D full core neutronic model was connected with 37 coolant channels thermal-hydraulic model of the core, 6-sector nodalization of reactor downcomer, lower and upper plenum was used. Mixing in lower and upper plenum was simulated. The first part of paper contains a brief characteristic of RELAP5 -3D system code and a short description of NPP input deck and reactor core model. The second part shows the time dependencies of important global and local parameters (Authors)

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Part of:
Proceedings of the thirteenth Symposium of Atomic Energy Research

Additional details

Publishing Information

Publisher
Kiadja and KFKI Atomenergia Kutatointezet
Imprint Place
Budapest (Hungary)
ISBN
963-372-630-1
Imprint Title
Proceedings of the thirteenth Symposium of Atomic Energy Research
Imprint Pagination
[833 p.]
Journal Page Range
p. 459-488
Report number
INIS-SK--2003-033

Conference

Title
13. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
Dates
22-26 Sep 2003
Place
Dresden (Germany)

Optional Information

Notes
11 refs., 29 figs., 5 tabs. Imprint:Next corporations organizations: VTT Energy, Technical Research Centre of Finland, P.O.Box 1604, FIN-02044 VTT (Finland); Fortum Nuclear Services Ltd., Rajatorpantie 8, Vantaa, POB 10-FIN-00048 FORTUM (FI); NPP Kozloduy, NPP 3321, Kozloduy (BG); Studsvik Scandpower AS (Norway); KFKI Atomic Energy Research Institute, Reactor Analysis Laboratory, H-1525 Budapest 114, POB 49 (Hungary); FZR - Forschungszentrum Rossendorf, Institute of Safety Research,P.O.Box 510119, D-01314 Dresden (Germany); Physics Faculty of Sofia University, Sofia (Bulgaria); NPP Kozloduy (Bulgaria); Framatome ANP GmbH, Erlangen (Germany); State Scientific and Technical Centre on Nuclear and Radiation Safety - 'SSTC N+RS', Radgospna st. 35-37, 03142 Kyiv (Ukraine); 'TUEV ENERGY CONSULT/TUEV' Sueddeutschland Bau und Betrib GmbH, Westendstrasse 199, 80868 Muenchen (Germany); Experimental +Design organization 'Gidropress', Podolsk (Russian Federation); Lappeenranta University of Technology, LUT, P.O.Box 20, FIN-53851 Lappeenranta (Finland); GRS - Gesellschaft fuer Anlagen - und Reactorsicherheit mbH (Germany); SE, a.s. - AE Bohunice, 919 31 Jaslovske Bohunice (Slovakia)