PRIZMA status

PRIZMA status

•PRIZMA is a Monte Carlo code for solving fixed source and criticality problems.•Particles: neutrons, gammas, electrons, positrons, ions.•Application fields: nuclear and radiation safety; pulsed, thermal and fast reactors.•PRIZMA is a part of package for precision core simulation through reactor cam...

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Bibliographic Details
Published in:Annals of nuclear energy Vol. 82; pp. 116 - 120
Main Authors: Kandiev, Y.Z., Kashaeva, E.A., Khatuntsev, K.E., Kuropatenko, E.S., Lobanova, L.V., Lukin, G.N., Malakhov, A.A., Malyshkin, G.N., Modestov, D.G., Mukhamadiev, R.F., Orlov, V.G., Samarin, S.I., Serova, E.V., Spirina, S.G., Vakhonina, T.V., Voronina, N.A., Zatsepin, O.V.
Format: Journal Article
Language:English
Published: Elsevier Ltd 01-08-2015
Subjects:
Constants
Criticality calculations
Mathematical models
Monte Carlo method
Nuclear engineering
Nuclear reactors
Particle transport
Positrons
PRIZMA code
Radiation transport
Three dimensional
Transport
Criticality calculations
Monte Carlo method
PRIZMA code
Particle transport
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Summary:•PRIZMA is a Monte Carlo code for solving fixed source and criticality problems.•Particles: neutrons, gammas, electrons, positrons, ions.•Application fields: nuclear and radiation safety; pulsed, thermal and fast reactors.•PRIZMA is a part of package for precision core simulation through reactor campaign.•Special techniques for perturbation analysis. For more than thirty years the code PRIZMA has been used at RFNC-VNIITF for solving radiation transport problems with the Monte Carlo method. The code models the separate and coupled transport of neutrons, photons, electrons, positrons and ions in one-, two-, and three-dimensional geometry. For criticality calculations the code implements the method of generations with a constant number of fission sites in one generation. Now the code is extending its capabilities for nuclear reactor calculations. The paper describes the current status of the code and gives examples of its application to particle transport in nuclear reactors and other physical facilities.
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ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2014.09.006