DOI: 10.55176/2414-1038-2019-2-31-37
Authors & Affiliations
Semenova T.V.1, Mitenkova E.F.2, Solovyova E.V.2
1 Russian Federal Nuclear Center, All-Russian Research Institute of Experimental Physics, Sarov, Russia
2 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
Semenova T.V. – Head of Laboratory, Cand. Sci. (Phys.-Math.), Russian Federal Nuclear Center, All-Russian Research Institute of Experimental Physics.
Mitenkova E.F. – Head of Laboratory, Cand. Sci. (Phys.-Math.), Nuclear Safety Institute of Russian Academy of Sciences. Contacts: 52, Bolshaya Tulskaya st., Moscow, Russia, 115191. Tel.: +7 (495) 955-22-02; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Solovyova E.V. – Senior Researcher, Cand. Sci. (Phys.-Math), Nuclear Safety Institute of Russian Academy of Sciences.
Abstract
In loosely coupled systems the criticality calculations using the traditional Monte Carlo power generation methods can lead to incorrect effective multiplication factor and neutron distribution functions, which is largely due to the steady-state neutron source in system. In reactor systems, the power generation method ensures the correct neutron source formation with a proper eigenfunction for any initial neutron distributions. A traditional power generation method does not guarantee the adequate source formation in loosely coupled systems even under very large calculation statistics. To count the neutron distribution functions in loosely coupled systems in TDMCC code is implemented algorithm based on fission matrix. Its capabilities are demonstrated to count the fission rate distributions in loosely coupled system such a slab with extended inhomogeneous fuel zones.
Keywords
Monte Carlo calculations, loosely coupled system, fission matrix, fission rate
Article Text (PDF, in Russian)
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UDC 004.94:621.039.51.17
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 2, 2:3
