Published 1995 | Version v1
Miscellaneous Open

Criticality safety of fresh and irradiated fuel of the 6.5 MW heavy water research reactor

  • 1. Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)

Description

Criticality safety problems, arising in away-from-reactor handling of the 6.5 MW heavy water research reactor fuel, are considered. The present status of fresh and spent fuel storage is described. To calculate criticality parameters of different non-reactor configurations of fresh and irradiated fuel, the well known WIMS code is combined with a few group three dimensional diffusion theory code TRITON. Typical results are presented and discussed. (author)

Availability note (English)

Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCA

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Additional details

Publishing Information

Publisher
Romanian Nuclear Energy Association 'AREN', University 'Politehnica' of Bucharest
Imprint Place
Bucharest (Romania)
Imprint Pagination
5 p.
Report number
INIS-RS--0994

Conference

Title
SIEN '95 - International symposium on nuclear energy
Original Conference Title
Proceeedings of SIEN '95 - International symposium on nuclear energy
Dates
20-21 Oct 1995
Place
Bucharest (Romania)

Optional Information

Notes
2 figs., 3 tabs., 4 refs. This record replaces record 27015769