Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.019 seconds
[en] A brief review of the codes available for the neutron-physical calculations of the heterogeneous nuclear reactors and critical assemblies is presented. These program can be used for simulation of the reactor part in the Accelerator Driven Transmutation Technology for Molten salt reactor Projects. Present review describes the programs that do not use empirical coefficients typical for the existing engineering program complexes intended for the calculation of thermal reactors. This is particularly important for the calculation of the non-standard situations in reactor as well as for designing the new reactor concepts. (Authors)
Source
Nuclear Power Plants Research Institute Trnava Inc., 918 64 Trnava (Slovakia); SKODA JS a.s., 316 06 Plzen (Czech Republic); Studsvik Scandpower, N-2027 Kjeller (Norway); KFKI Atomic Energy Research Institute, H-1525 Budapest (Hungary); NPP of Paks, Paks (Hungary); Dukovany NPP, 675 50 Dukovany (Czech Republic); Nuclear Research Institute Rez plc, Rez (Czech Republic); Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Science, Sophia (Bulgaria); NPP Kozloduy, Kozloduy (Bulgaria); Fortum Engineering Ltd., Vantaa (Finland); [780 p.]; ISBN 963-372-616-6; 
; Oct 1999; p. 761-770; 9. Symposium of Atomic Energy Research; Demanovska Dolina (Slovakia); 4-8 Oct 1999; Also available from Nuclear Power Plants Research Institute Trnava a.s., Okruzna 5, 918 64 Trnava (Slovak Republic); 25 refs.
; Oct 1999; p. 761-770; 9. Symposium of Atomic Energy Research; Demanovska Dolina (Slovakia); 4-8 Oct 1999; Also available from Nuclear Power Plants Research Institute Trnava a.s., Okruzna 5, 918 64 Trnava (Slovak Republic); 25 refs.