Authors & Affiliations
Koscheev V.N., Rozikhin E.V., Yakunin A.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Koscheev V.N. – Leading Research, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, Bondarenko sq., Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-42-65; e-mail:
Rozikhin E.V. – Senior Research, A.I. Leypunsky Institute for Physics and Power Engineering.
Yakunin A.A. – Research Associate, A.I. Leypunsky Institute for Physics and Power Engineering.
The paper presents the results of validation for the capture cross section of the main fission product (FP) nuclides from different neutron data libraries on the results of measurements in integral experiments. A list of the main fission products for various types of fast reactors with various burnups of fuel is defined.
When fissioning fuel nuclides in a nuclear reactor, numerous fission products are formed. The most important characteristic of fission products is the neutron capture cross section, as a result of which the valuable neutron for maintaining the fission chain reaction disappears. During long campaigns, the accumulated fission products can lead to a decrease in the criticality of the reactor to ~ 7%. The evaluated neutron data for the main set of FP nuclides are contained in national libraries of evaluated neutron data. Evaluation of neutron data, as a rule, is carried out on the basis of experimental data from the international EXFOR database using various computational models of nuclear interactions. Often, the evaluated data is very different from each other.
Evaluated data can be tested using integral experiments. To test the capture cross section for FP nuclides, direct integral experiments at the CFRMF reactor and experiments in which the neutron spectrum is close to the Maxwell spectrum with a spectrum temperature of kT = 30 keV were used. The first of the above experiments is a dosimetric benchmark experiment, given in the ENDF-202 benchmark experiment handbook. The second type of experiment underlies the recommendations for the MACS capture cross section for nuclides from the KADONiS astrophysical database.
fast reactors, fuel nuclides, fission products, capture cross section, libraries of evaluated neutron data, testing, direct integral benchmark tests, CFRMF reactor, KADONiS astrophysical base
1. Cibulya A.M. Kochetkov F.L. Kravchenko I.V. Nikolaev M.N. K opisaniu pogloscheniya neitronov v produktah deleniya put'em vvedeniya psevdooskolka [A description of neutron absorption in fission products by introducing a pseudo-fragment]. Voprosy atomnoy nauki i tekhniki. Seriya:Yadernye konstanty - Problems of atomic science and technology. Series: Nuclear Constants, 1985, no. 4, pp. 71.
2. А report of the Working Party on International Evaluation Co-operatio of the NEA Nuclear Science Committee. Vol. 17. Status of Psevdo-Fission-Product Cross-Sections for Fast Reactors. NEA/WPEC-17, ENC-R-98-014. OECD-1998.
3. Matveev V.I., Chebeskov A.N., Cherny V.A. et al. Studies, Development and Justification of Core with Zero Sodium Void Reactivity Effect of the BN-800 Reactor. Proc. Int. topical meeting on Sodium Cooled Fast Reactor Safety. Obninsk, 1994.
4. Khomyakov Yu.S., Eliseev V.A., Malysheva V.I. et al. Optimization of Parameters of MOX Fuel Core of Sodium Cooled Large Size Fast Reactor. Proceedings of Global 2009. Paris, France, 2009.
5. Zrodnikov A.V., Dragunov U.G., Stepanov V.S., Toshinsky G.I. et al. SVBR-75/100 – Lead-bismuth cooled small power modular fast reactor for multipurpose usage. Proc. Int. Сonf. “Innovative Technologies for Nuclear Fuel Cycles and Nuclear Power”. Vienna, 2003, pp. 371.
6. Smirnov V., Orlov V. The lead cooled fast reactor benchmark BREST-300: analysis with sensitivity method. Proc. Conf. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Palais des Papes. Avignon, France, 2005.
7. Evaluated Nuclear Data Library database. Available at: https://www-nds.iaea.org/exfor/endf.htm (assecced 13.10.2019).
8. EXFOR – Experimental Nuclear Reaction Data database. Available at: www-nds.iaea.org/exfor/exfor.htm (assecced 13.10.2019).
9. Cross Section Evaluation Working Group Benchmark Specifications (Dosimetry benchmark No 1). ENDF-202 BNL-19302, Volume II, Brookhaven National Laboratory, Upton (1991).
10. Hanker Y., Anderl R. Neodymium, Samarium and Europium Capture Cross Section Adjustments Based on EBR-II Integral Measurements. Proc. Meeting on Neutron Cross Sections of Fission Product Nuclei. Bologna, Italy, 1979.
11. Dillmann I., Szucs T., Plag R. et.al. The Karlsruhe Astrophysical Database of Nucleosynthesis in Stars Project – Status and Prospects. Nuclear Data Sheets, 2014, vol. 120, pp. 171.
12. Bednyakov S.M., Manturov G.N. Testirovanie i utochnenie sechenii zakhvata produktov deleniya v eksperimentah po vozmuscheniu reactivnosti [Testing and refinement of capture cross sections for fission products in experiments on reactivity perturbation]. Atomnaya energiya – Atomic Energy, 1992, vol. 72, no. 1, pp. 95–98.
13. Dietze K. The Rossendorf RRR/SEG-Facility (Documentation) Note Technique SPRC/LEPH/93-230, Cadarache, 1993.
14. Veenema J.J., Janssen A.J. Small-sample reactivity worths of fission product isotopes and some other materials measured in STEK, ECN-10 Petten, 1976.
15. Astrofizicheskaya baza dannykh KADONiS [Astrophysical Database KADONiS]. Available at: https://exp-astro.de/kadonis1.0/ (assecced 13.10.2019).