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Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark – re-connection of an isolated loop

Qualifizierung von gekoppelten 3D-Neutronenkinetik-Thermohydraulik-Programmsystemen am Beispiel von Rechnungen zum VVER-440 Benchmark „Wiederinbetriebnahme eines isolierten Loops“
  • A. Kotsarev , M. Lizorkin , M. Benčík , J. Hádek , Y. Kozmenkov and S. Kliem
From the journal Kerntechnik

Abstract

The 7th AER dynamic benchmark is a continuation of the efforts to validate the codes systematically for the estimation of the transient behavior of VVER type nuclear power plants. The main part of the benchmark is the simulation of the re-connection of an isolated circulation loop with low temperature in a VVER-440 plant. This benchmark was calculated by the National Research Centre “Kurchatov Institute” (with the code ATHLET/BIPR-VVER), ÚJV Řež (with the code RELAP5-3D©) and HZDR (with the code DYN3D/ATHLET). The paper gives an overview of the behavior of the main thermal hydraulic and neutron kinetic parameters in the provided solutions.

Kurzfassung

Der 7. dynamische AER Benchmark führt die Arbeiten zur systematischen Validierung der Programme zur Berechnung von transientem Verhalten in WWER Reaktoren weiter. Der größte Teil dieses Benchmarkproblems widmet sich der Berechnung der Wiederinbetriebnahme eines isolierten Loops mit Kühlmittel niedriger Temperatur in einem WWER-440. Dieser Benchmark wurde vom National Research Centre “Kurchatov Institute” (mit dem Programmsystem ATHLET/BIPR-VVER), ÚJV Řež (RELAP5-3D©) und dem HZDR (DYN3D/ATHLET) berechnet. In diesem Beitrag werden die wesentlichen berechneten Parameter der Thermohydraulik und der Neutronenkinetik verglichen.


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Received: 2016-01-28
Published Online: 2016-08-10
Published in Print: 2016-08-26

© 2016, Carl Hanser Verlag, München

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