European Validation of the Integral Code ASTEC (EVITA)

Allelein, Hans-Josef; Neu, K.; Dorsselaere, J.P. Van

doi:10.1016/j.nucengdes.2004.08.051

Cited by 15 publications

(1 citation statement)

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“…To simulate the corium melting pool phenomena in the LP during the vessel external water cooling the ICARE and CESAR modules of ASTECv2.2b computer has been used. The developers of the ASTEC (Accident Source Term Evaluation Code) computer code [3,4] for simulation of severe accidents at light water reactors are the French Institut de Radioprotection et de Sûreté Nucléaire (IRSN) and the German Gesellschaft für Anlagen und Reaktorsicherheit (GRS). The ASTEC code is currently under development by IRSN [5,6,7].…”

Section: Introductionmentioning

confidence: 99%

ASTECV2.2b and SUNSET uncertainty and sensitivity analyses on IVMR WWER1000 Test Case

Gencheva,

Stefanova,

Groudev

2023

Proceedings of 11th International Conference of the Balkan Physical Union — PoS(BPU11)

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This article concerns an uncertainty and sensitivity investigation of certain parameters in the In-Vessel Melt Retention (IVMR) test case for Water-Water Energetic Reactor -1000/v320 (WWER-1000/v320). It has been used the ICARE and CESAR modules of ASTECv2.2b severe accident computer code to describe the basic parameters behaviour and the main phenomena arising during the IVMR in WWER1000 reactor design. The external vessel water cooling has been chosen for IVMR strategy. First, one stand-alone calculation have been done to account the most heat loaded segment from the vessel.After, the uncertainties in two parameters in the deterministic calculation have been investigated additionally to account their influence on the heat flux on this segment. An opportunity for an uncertainty and sensitivity analyses gives SUNSET (Statistical UNcertainty and Sensitivity Evaluation Tool) software which is a part of ASTEC computer code. The SUNSET computational tool developed by IRSN, is a statistical tool designed for uncertainty and sensitivity analysis of mathematical or physical models like computer codes.It have been investigated an influence of the different pressure values inside the vessel and influence of the different temperature values of outside cooling water on the two basic output parameters: heat flux on the most heat loaded segment of the vessel and the minimal vessel wall thickness of this segment. It was found out to what extent each one of the both input parameters effect on the studied output parameters.

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Section: Introductionmentioning

confidence: 99%