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Present status of the NET IBK computer code package for in-core fuel management and related core parameter calculations 

Mataušek, M. V.; Marinković, N.; Petrović, Ivan M.; Zavaljevski, N.; Milošević, M. (IAEA: Technical committee meeting and workshop on improvements of in-core fuel management codes; Madrid (Spain); 12-15 Jul 1988, 1990)
This paper presents and discusses the current status of the NET IBK (Nuclear Engineering Department of the Boris Kidric Institute of Nuclear Sciences) computer code package for nuclear analysis of power reactors and in-core ...
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Calculational and experimental investigations of void effect. A new model for leakage treatment of heterogeneous assemblies 

Benoist, Pierre; Petrović, Ivan M.; Mondot, Jacques (International conference on mathematical methods and supercomputing in nuclear applications; Karlsruhe (Germany); 19-23 Apr 1993., 1993)
The growing interest in safety problems had led physicists to try to increase their knowledge of the neutron leakage phenomenon, both by calculation and by experiment The flux calculation in a heterogeneous assembly is ...
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''TIBERE'' a calculational method of the effect of lattice heterogeneity on the neutron leakage / ''TIBERE'' une methode de calcul de l'effet de l'heterogeneite d'un reseau sur les fuites de neutrons 

Benoist, Pierre; Petrović, Ivan M. (CEA Centre d'Etudes de Saclay, Dept. de Mecanique et de Technologie (France), 1992)
The flux calculation in a heterogeneous assembly in APOLLO and APOLLO-2 codes is based on the collision probability method On the contrary, the neutron leakage calculation is accomplished for a flux-weighted homogenized ...
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Improvements in the calculational methods of nuclear reactor assemblies 

Benoist, Pierre; Petrović, Ivan M.; Stankovski, Z. (Specialists meeting on advanced calculational methods for power reactors; Technical committee meeting and workshop on LWR core design parameters, 1992)
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calculating this rate for a homogeneous medium representing approximately the assembly, but not the leakage rate of the assembly ...
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SRNA: a Monte Carlo code for proton transport simulation 

Ilić, R.; Petrović, Ivan M. (6. Workshop on heavy-charged particles in biology and medicine; Baveno (Italy), 1997)

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