Verifcation of ABBN constants and CONSYST code in criticality calculations

УДК 621.039.51.17

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The aim of current work is verification of uptodate BNAB neutron constants library and
CONSYST code for neutron constants preparation via calculations of a set of simplified
calculation models of nuclear power systems and critical experiments from international
handbook ICSBEP.
There is the description of uptodate version of BNAB neutron constants library which
was obtained from evaluated neutron data files RUSFOND2010 and intended for perspective
fast reactor models calculations in current paper materials. The verification process is based
on calculation results comparisons for numerous benchmarkmodels of critical experiments
and simplified models of nuclear power systems – «Pruvost curves» – calculated by means
of MMKKENO code with MCNP calculation results. The comparison with experimental data
was made. Based on benchmarkexperiments with fast neutron spectra the results of testing
of neutron constants preparation method laid in uptodate version of CONSYST code with
BNAB neutron constants is given in paper. These results were obtained by means of
comparison with calculation results using BNAB crosssections prepared by TRANSX code.
Following the results of performed work a key conclusion have been made that the
methodical uncertainty caused by applying the groupwise approach is estimated as less
than ±0.2% Δk/k.

1. Manturov G.N., Nikolaev M.N., Tsibulya A.M. Programma podgotovki konstant CONSYST. Opisanie primenenija: Preprint GNC RFFEI2828. [CONSYST code for neutron constants preparation. Scope statement: IPPE Preprint2828]. Obninsk, FEI Publ., 2000. (in Russian)
2. Manturov G.N., Nikolaev M.N., Tsibulya A.M. Sistema gruppovyh konstant BNAB93. Chast’ 1: Jadernye konstanty dlja rascheta nejtronnyh i fotonnyh polej izluchenij [BNAB 93 group data library. Part 1: Nuclear data for calculation of neutron and photon radiation fields]. Voprosy atomnoj nauki i tehniki. Yadernye konstanty. 1996, no. 1, p.59.
3. MacFarlane R.E. et al. NJOY97.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Sections from ENDF/B Data. RSIC Peripheral Shielding Routine Collection, PSR368.
4. Zabrodskaja S.V., Ignatjuk A.V., Koscheev V.N., Manohin V.N., Nikolaev M.N., Pronjaev V.G. ROSFOND  rossijskaja nacional’naja biblioteka ocenennyh nejtronnyh dannyh [RUSFOND – Russian national evaluated neutron data library]. Voprosy atomnoj nauki i tehniki. Yadernye konstanty. 2007, no. 12, pp.321.
5. DANTSYS 3.0: One, Two, and Three Dimensional, Multigroup, Discrete Ordinates Transport Code System. RSIC Computer Code Collection, CCC547, ORNL (1993).
6. «MCNP – A General Monte Carlo NeutronParticle Transport Code». Version 5. X5 Monte Carlo Team, Los Alamos National Laboratory, April 2003.
7. Bliskavka A.A., Manturov G.N., Nikolaev M.N., Tsibulya A.M. Programmnyj kompleks CONSYST/MMKKENO dlya rascheta yadernyh reaktorov metodom MonteKarlo v mnogogruppovom priblizhenii s indikatrisami rassejaniya v PNpriblizhenii. Preprint GNC RFFEI2887. [CONSYST /MMKKENO code package for nuclear reactor calculations with MonteCarlo in multigroup PNapproximation: IPPE Preprint2887]. Obninsk, FEI Publ., 2001. (in Russian).
8. MacFarlane R.E. «TRANSX 2: A Code for Interfacing MATXS CrossSection Libraries to Nuclear Transport Codes», Los Alamos National Laboratory 1992.
9. «International Handbook of Evaluated Criticality Safety Benchmark Experiments», Organization for Economic Cooperation and Development – Nuclear Energy Agency, NEA/ NSC/DOC(95)03 (September 2002 Edition).
10. Pruvost Norman L., Paxton Hugh C. Nuclear Criticality Safety Guide, LA12808, UC714 (1996).

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