THE UPGRADE OF NEUTRON DATA LIBRARIES AND THE SAPFIR_95 PROGRAM INTENDED FOR REACTOR CELLS CALCULATIONS

ISSUES

Authors & Affiliations

Ivanov A.S., Karpov A.S.
Alexandrov Research Institute of Technoloqy, Sosnovy Bor, Russia

Ivanov A.S. – Cand. Sci. (Tech.), Alexandrov Research Institute of Technoloqy.
Karpov A.S. – Senior Researcher, Alexandrov Research Institute of Technoloqy. Contacts: 72, Koporskoe shosse, Sosnovy Bor, Leningrad region, Russia, 188540. Tel.: +7(81369) 6-08-83; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

The SAPFIR_95 program based on the many-group neutron data libraries calculates neutronic characteristics of reactor cells during the fuel burnup. ABBN 78/S 95 many-group library is used together with the certified version of the program.
Today the new many-group neutron data library is received and the new fuel burnup scheme is developed on the basis of the modern evaluated nuclear data files of ROSFOND. Cross sections libraries and burnup schemes are formed automatically using NJOY-B30 system. Neutron cross section libraries in epithermal region use 23-groups of the ABBN system and 40-group representation for thermal region. The fuel burnup scheme plainly considers around four hundred of fission fragments and actinides. Fission yield in the scheme is specified with regard to the energy of the neutrons that cause the fission of fuel nuclides. It helps to create the uniform scheme of fuel burnup for both thermal and fast reactors.
The SAPFIR_95 program is considerably upgraded as well. First, the segment of fuel burnup calculation has been completely revised. The new algorithm does not use the approach of effective fission fragment anymore and considers all significant fission fragments. Neutron cross-sections of fission fragments are presented in the many-group form considering the factors of resonant self-screening in the region below the 15th group. New version of the program does not use the simulated fission spectrum and considers the actual spectrums of fission neutrons of the main fissile materials. Matrixes of inelastic processes and ranges of fission neutrons are increased by one group. The resonance correlation algorithm when using the generalized subgroup approach is developed for region of the resolved resonances.
This paper describes the structure of neutron data libraries and upgraded algorithms. The results of test calculations using the new libraries and fuel burnup schemes are given.

Keywords
cells of reactor calculation, SAPFIR_95 program, evaluated ROSFOND and ENDF/B-VII data, group constant, fuel burnup

Article Text (PDF, in Russian)

References

1. Programma rascheta neytronno-fizicheskikh kharakteristik yacheek reaktorov SAPFIR_95.1 [Program for calculating the neutron-physical characteristics of the cells of the SAPPHIRE_95.1 reactors]. Certification passport - 280, 16.12.2015.

2. Programma rascheta neytronno-fizicheskikh kharakteristik reaktora SAP-FIR_95&RC_VVER.2 [Program for calculating the neutron-physical characteristics of the reactor SAP-FIR_95&RC_VVER2]. Certification passport - 321, 18.04.2013.

3. Data Formats and Procedures for Evaluated Nuclear Data File ENDF/B VI and ENDF/B VII. Report Brookhaven National Laboratory NCS 44945 05 Rev., 2005.

4. Zabrodskaya S.V., Ignatyuk A.V., Koshcheev V.N., Manokhin V.N., Nikolaev M.N., Pronyaev V.G. ROSFOND – rossiyskaya natsional'naya biblioteka otsenennykh neytronnykh dannykh [RUSFOND – russian national library of evaluated neutron data]. Voprosy Atomnoy Nauki i Tekhniki. Seriya: Yaderno-reaktornye konstanty Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constans, 2007, no. 1-2, pp. 3-21.

5. Karpov A.S., Tebin V.V. NJOY-B30 – sistema podgotovki mnogogruppovykh konstant na osnove otsenennykh yadernykh dannykh v pakete SAPFIR [NJOY-B30 is a system for preparing multi-group constants based on the estimated nuclear data in the SAPPHIRE package]. Trudy 10 Mezhdunarodnogo seminara po problemam fiziki reaktorov [Proc. 10th Int. Seminar on Problems of Reactor Physics]. Moscow, 1997.

6. Tebin V.V., Udkevich M.S. Obobshchennyy podgruppovoy podkhod k raschetu rezonansnogo pogloshcheniya [Generalized subgroup approach to the calculation of resonant absorption]. Atomnaya energiya - Atomic Energy, 1985, vol. 59, no. 2, pp. 96.

7. MacFarlane R.E. et al. NJOY 87.0, LANL Memo T-2-L10991.

8. Galanin A.D. Approksimatsiya pogloshcheniya neytronov produktami deleniya odnim effektivnym oskolkom [Approximation of neutron absorption by fission products by one effective fragment]. Atomnaya energiya - Atomic Energy, 1981, vol. 50, no. 1, pp. 3-6.

9. Karpov A.S. Modernizatsiya skhemy vygoraniya topliva v programme SAPFIR_95 [Modernization of the burnup scheme in the SAPPHIRE_95 program]. Tekhnologii obespecheniya zhiznennogo tsikla YaEU - Technologies for ensuring the life cycle of nuclear power plants, 2015, vol. 1, no. 1, pp. 62-68.

10. Karpov A.S. Modernizatsiya spektral'noy zadach programmy SAPFIR_95 [Modernization of the spectral tasks of the SAPPHIRE_95 program], (2013). Available at: http://www.niti.ru/3_press-center/3_3_public/report_niti_2015.pdf (accessed 12.09.2017).

11. Akimushkin S., Avvakumov A., Malofeev V., Roslykov A. LWR MOX Benchmark Calculations Using the BARS Code. NSIRNRKI 90-12/1-12-01. Moscow, 2001.

12. Benchmark Calculations of Power Distribution within Fuel assemblies. NEA/NSC/DOC, 2000.

13. Belousov N.I., Davidenko V.D., Tsibul'skiy V.F. Programma UNK dlya detal'nogo rascheta spektra neytronov v yacheyke yadernogo reaktora [UNK program for detailed calculation of the neutron spectrum in the cell of a nuclear reactor]. Preprint RNTs "Kurchatovskiy Institut" IAE-6083.4 - Preprint of the RRC "Kurchatov Institute", IAE-6083.4. Moscow, 1998.

UDC 621.039.51

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 1, 1:3

BROND-3.1

ISSUES

2018, Issue 1

THE UPGRADE OF NEUTRON DATA LIBRARIES AND THE SAPFIR_95 PROGRAM INTENDED FOR REACTOR CELLS CALCULATIONS