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Projects / Programmes source: ARIS

Nevtronika sredice jedrskih reaktorjev (Slovene)

Research activity

Code Science Field Subfield
1.07.00  Natural sciences and mathematics  Computer intensive methods and applications   

Code Science Field
P220  Natural sciences and mathematics  Nuclear physics 
T160  Technological sciences  Nuclear engineering and technology 
Keywords
nuclear reactor, reactor calculations, nuclear data, criticality benchmark, fuel management, Monte-Carlo calculations
Evaluation (rules)
source: COBISS
Researchers (12)
no. Code Name and surname Research area Role Period No. of publicationsNo. of publications
1.  01116  PhD Milan Čerček  Physics  Researcher  1996 - 2001  318 
2.  06743  PhD Bogdan Glumac  Energy engineering  Researcher  1998 - 2001  132 
3.  03590  PhD Igor Jenčič  Physics  Researcher  1996 - 2001  151 
4.  01053  Edvard Stanisla Krištof  Energy engineering  Researcher  1996 - 2001  46 
5.  04538  PhD Marjan Kromar  Energy engineering  Researcher  2000 - 2001  300 
6.  14625  PhD Marko Maučec  Energy engineering  Researcher  1996 - 2001  142 
7.  05097  PhD Matjaž Ravnik  Energy engineering  Head  1998 - 2001  439 
8.  15739  Dušan Rudman    Researcher  1999 - 2001 
9.  07991  Slavko Slavič  Energy engineering  Researcher  1998 - 2001  94 
10.  12165  PhD Mladen Stanojević  Computer science and informatics  Researcher  1998 - 2001  84 
11.  08557  PhD Andrej Trkov  Energy engineering  Researcher  1998 - 2001  795 
12.  15742  Bojan Žefran    Researcher  1998 - 2001  152 
Organisations (1)
no. Code Research organisation City Registration number No. of publicationsNo. of publications
1.  0106  Jožef Stefan Institute  Ljubljana  5051606000  90,724 
Abstract
The following experiental and theoretical reactor physics problems are treated in the project: nuclear data processing for unit-cell and Monte-Carlo calculations based on modern nuclear data evaluations, development and evaluation of experimental bench-mark test cases for TRIGA reactor with fresh and partly burned fuel, development of new methods for burn-up distribution calculation in the research reactor core containing strong burnable absorbers, research and development of computational efficient methods for multigroup constants tabulating based on reactivity coefficients method and development of Monte-Carlo models for neutron and gamma transport calculations in realistic geometry. The results of the project may be applied to practical methods for research reactor fuel burn-up determination, to development and testing of computer codes for TRIGA and PWR core management and to criticality safety analysis of nuclear fuel in the reactor and in the spent fuel storage.
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