Lomakov G.B.1, Nikolaev M.N.1, Filippov V.V.2
1A.I. Leypunsky Institute for Physics and Power, Obninsk, Russia
2Obninsk Institute for Nuclear Power Engineering (IATE MEPHI), Obninsk, Russia
Experiments on measurements of a transmission neutron function in fast energy region for wide set of elements were conducted in 1960s (IPPE, Russia). Transmission’s function is included in the transport of neutrons equation and it used in all modern calculated codes. Thus obtaining a real component of this equation allows increase reliability of nuclear data used in calculations. In this work described experimental facilities, physics of experiment and are presented formulas for calculating transmission function and its uncertainty. The paper is an introductory part for next series of papers with evaluation of measured transmission function. In this series of works were evaluated uncertainty of measured values, were identified deviations from correct course of transmission function curve, was evaluated background flux, were determined energy bounds, spectrum of neutrons and average total cross section. Evaluated results were compared with calculated using nuclear data libraries.
1. Bell G., Glasston S. Nuclear Reactor Theory. New York, 1970.
2. Bondarenko I.I. Group Constants for Nuclear Reactor Calculations. New York, Consultants Bureau Publ., 1964.
3. Bondarenko I.I., Nikolaev M.N., Filippov V.V. The Effect of the Resonance Structure of Cross Sections on the Propagation of Fast Neutrons in Iron. Atomic Energy, 1962, vol. 11, no.5, pp. 1090-1093.
4. Abagyan L.P., Bazazyants N.O., Nikolaev M.N., Tsibulya A.M. Gruppovye konstanty dlya rascheta reaktorov i zaschity [The Group Constant Set for Reactor and Shielding Calculation] Moscow, Energoizdat Publ., 1981.
5. Levitt L.B. The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations. Nuclear Science and Engineering, 1972, vol.49, pp.450-57.
6. Grigor’ev Yu.V., Gundorin G.N., Popov Yu.P., Sinitsa C.C., Fajkov-Stanchik Kh. Investigation of Neutron Cross-section for Thorium-232 and Neptunium-237 in Energy Range 2 eV – 100 keV. Voprosy atomnoy nauki i tekhniki. Ser. Yadernye konstanty – Problems of atomic science and technology. Series: Nuclear Constants, 1998, no.1, pp. 13-21. Available at: http://vant.ippe.ru/images/pdf/1998/1-2.pdf (accessed 26 February 2016).
7. Measurement of Fast Neutron Transmission Through Iron, Nickel, and Chromium Samples of Various Thicknesses (FUND-IPPE-VDG-MULT-TRANS-001). ICSBEP Handbook. 2011, vol. IX.
8. Nikolaev M.N. Filippov V.V. Measurement of Total Cross-section Resonance Structure Parameters for Some Elements in the Energy Region 0,3–2,7 MeV. Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology, 1964, vol. 18, no.8, pp. 471-478.
9. Nikolaev M.N., Filippov V.V. Measurement of Total Cross-section Structure. Proc. Conf. "Nuclear Data for Computations Sem". Dubna, 1968.
10. Borisov G.A., Vasil’ev R.D., Shevchenko V.F. Kinematic Tables of Nuclear Reactions d,n and p,n. Moscow, 1974.
11. Mariona Dzh., Faulera Dzh. Fast Neutron Physics. Part 1: Techniques. New York, 1960.
12. IAEA. Handbook on Nuclear Activation Data. Technical Reports Series 273. Vienna, 1987. 83p.
13. MCNP – A General Monte Carlo N-Particle Transport Code. Volume II: User’s Guide”, LA-CP-03-0245 (April, 2003).
14. Zabrodskaya S.V., Ignatyuk A.V., Koscheev V.N., Manokhin V.N., Nikolaev M.N., Pronyaev V.G. ROSFOND – Rossijskaya nacional’naya biblioteka ocenennyh nejtronnyh dannyh [ROSFOND – The National Library of Evaluated Neutron Data]. Voprosy atomnoy nauki i tekhniki. Ser. Yadernye konstanty – Problems of atomic science and technology. Series: Nuclear Constants, 2007, no.1-2, pp. 3-21. Available at: http://vant.ippe.ru/images/pdf/2007/1.pdf (accessed 26 February 2016).
15. Chadwick M.B., Herman M., Oblozinsky P., et al. ENDF/B-VII.1 nuclear data for science and technology: Cross sections, covariances, fission product yields and decay data. Nuclear Data Sheets, 2011, vol.112, no.12, pp.2887-2996.
16. Shibata K., Iwamoto O., Nakagawa T., Iwamoto N., Ichihara A., Kunieda S., Chiba S., Furutaka K., Otuka N., Ohsawa T., Murata T., Matsunobu H., Zukeran A., Kamada S., Katakura J. JENDL-4.0: A
New Library for Nuclear Science and Engineering. Nuclear Science and Technology, 2011, vol.48, no.1, pp.1-30.
17. Kopecky J. Final Verification and Validation of JEFF-3.2. JEF/DOC-1590.
18. Koning A.J., Rochman D., van der Marck S.C, Kopecky J., Sublet J.Ch., Pomp S., Sjostrand H., Forrest R., Bauge E., Henriksson H., Cabellos O., Goriely S., Leppanen J., Leeb H., Plompen A., Mills R., Hilaire S. TENDL-2014: TALYS-based evaluated nuclear data library (2013). Available at: ftp://ftp.nrg.eu/pub/www/talys/tendl2013/tendl2013.html (accessed 26 February 2016).
