THE ASTEC INTEGRAL CODE FOR SEVERE ACCIDENT SIMULATION

For several years the French Institut de Radioprotection et de Sarete Nucliaire (IRSN) and the German Gesellschaft far Anlagen and Reaktorsicherheit (GRS) mbH have been jointly developing a system of calculation codes - the integral Accident Source Term Evaluation Code (ASTEC) - to simulate the comp...

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Bibliographic Details
Published in:Nuclear technology 2009-03, Vol.165 (3), p.293-307
Main Authors: VAN DORSSELAERE, J. P, SEROPIAN, C, CHATELARD, P, JACQ, F, FLEUROT, J, GIORDANO, P, REINKE, N, SCHWINGES, B, ALLELEIN, H. J, LUTHER, W
Format: Article
Language:English
Subjects:
Applied sciences
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Installations for energy generation and conversion: thermal and electrical energy
Online Access:Get full text
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Summary:For several years the French Institut de Radioprotection et de Sarete Nucliaire (IRSN) and the German Gesellschaft far Anlagen and Reaktorsicherheit (GRS) mbH have been jointly developing a system of calculation codes - the integral Accident Source Term Evaluation Code (ASTEC) - to simulate the complete scenario of a hypothetical severe accident in a nuclear light water reactor, from the initial event until the possible radiological release of fission products out of the containment, i.e., the source term. ASTEC has progressively reached a larger European dimension through projects of the European Commission Framework Programme.
ISSN:0029-5450
1943-7471
DOI:10.13182/NT09-12