Open Access
Issue
ND 2007
2007
Article Number 224
Number of page(s) 4
Section Benchmarking for fission applications
DOI https://doi.org/10.1051/ndata:07480
Published online 17 June 2008
International Conference on Nuclear Data for Science and Technology 2007
DOI: 10.1051/ndata:07480

LWR decay heat calculations using a GRS improved ENDF/B-VI based ORIGEN data library

U. Hesse, Kl. Hummelsheim, R. Kilger, F.E. Moser and S. Langenbuch

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Forschungsinstitute, 85748 Garching, Germany

Ulrich.Hesse@grs.de

Published online: 21 May 2008

Abstract
The known ORNL ORIGEN code is widely spread over the world for inventory, activity and decay heat tasks and is used stand-alone or implemented in activation, shielding or burn-up systems. More than 1000 isotopes with more than six coupled neutron capture and radioactive decay channels are handled simultaneously by the code. The characteristics of the calculated inventories, e.g., masses, activities, neutron and photon source terms or the decay heat during short or long decay time steps are achieved by summing over all isotopes, characterized in the ORIGEN libraries. An extended nuclear GRS-ORIGENX data library is now developed for practical appliance. The library was checked for activation tasks of structure material isotopes and for actinide and fission product burn-up calculations compared with experiments and standard methods. The paper is directed to the LWR decay heat calculation features of the new library and shows the differences of dynamical and time integrated results of ENDF/B-VI based and elder ENDF/B-V based libraries for decay heat tasks compared to fission burst experiments, ANS curves and some other published data. A multi-group time exponential evaluation is given for the fission burst power of 4 important fission materials, to be used in quick LWR reactor accident decay heat calculation tools.



© CEA 2008

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