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AbstractAbstract
[en] The need for reducing the intrinsic conservatism in the criticality safety assessment has led to the development of validated methods for assessing the reactivity effects associated with fuel burnup. This paper gives an overview of the work being performed to investigate the spent fuel characteristics and nuclear criticality safety of the reactor RA spent fuel storage. An analysis methodology is presented along with information representing the validation of the methods and geometrical models. Finally, the criticality safety analysis of the stainless steel containers and aluminum barrels, filled with spent fuel elements, is presented to demonstrate that an adequate margin of subcriticality is proved for the reactor RA spent fuel storage.(author)
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Secondary Subject
Source
2001; 14 p; Institute of Nuclear Sciences VINCA, Belgrade, Yugoslavia; Belgrade (Yugoslavia); International Yugoslav Nuclear Society Conference (YUNSC-2000); Konferencija Jugoslovenskog nuklearnog drustva (YUNSC-2000); Belgrade (Yugoslavia); 2-5 Oct 2000; ISBN 86-7306-049-4;
; Also available from Institute of Nuclear Sciences VINCA; 25 refs., 7 figs., 9 tab., This record replaces 33044864

Record Type
Miscellaneous
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ALLOYS, CALCULATION METHODS, CARBON ADDITIONS, CASKS, COMPUTER CODES, CONTAINERS, DATA, DIMENSIONLESS NUMBERS, DIRECT ENERGY CONVERTERS, ELECTROCHEMICAL CELLS, ELEMENTS, ENRICHED URANIUM REACTORS, EVALUATION, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, METALS, NUMERICAL DATA, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, STEELS, STORAGE, TANK TYPE REACTORS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS
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