SOME ISSUES OF MODELING OF DESIGN TECHNOLOGY OF NEW REACTORS BASED ON THE PHYSICOCHEMICAL PROPERTIES OF MOX-FUEL


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Abstract

To the issue of modeling of design technology of new reactors based on the physicochemical properties of MOX-fuel, the authors considered the existing mathematical models for estimation of neutronics and radiation characteristics of the main experimental volumes using the example of the designed fast research reactor. The efficient use of MOX-fuel is achieved when combusting it in fast reactors; and its production is possible by processing irradiated fuel of power reactors. The use of MOX-fuel in existing reactors requires significant alterations (introduction of more control rods), but it will be possible in full in specially designed MBIR reactor. One of the attractive properties of MOX-fuel is that during its production it is possible to dispose the extra amount of weapon grade plutonium, which otherwise would be the radioactive wastes. For central serpentine passage, the authors get the estimations of average and maximum neutron flux density, axial distribution of neutron flux density that is actual for the issue of radiation resistance of the materials used in modern reactor engineering. The design model is developed on the basis of MCU applied software package (MCU-RR2 version) implementing the paradigm of Monte-Carlo method when drawing the traces of neutrons and gamma-quanta in 3D geometry for mutual simulation of neutrons and photons flux functionality in the research nuclear reactors, basing on the estimated nuclear data. 

For vertical experimental channel, the authors determined the dependences of specific induced activity and induced activity of commercial nitrogen gas on the operation time of reactor in order to ensure the cost-effectiveness of the materials used for the cooling of channel supposed for the nuclear doping of silicon. Simulation of the cooling environment activation was carried out by means of mathematical modeling of kinetics of nuclide transformations according to the UPM-PREPRO_2007-FENDL-2.0-ENDF/B-VII.0 software complex, where PREPRO_2007 is the package of utilities for the preprocessing of nuclear data in ENDF/B format.

About the authors

Alla Ravilievna Belozerova

State Scientific Center – Research Institute of Atomic Reactors, Dimitrovgrad

Email: asabel2009@yandex.ru

candidate of physical and mathematical sciences, senior researcher

Россия

Elena Sergeevna Komarova

State Scientific Center – Research Institute of Atomic Reactors, Dimitrovgrad

Email: elena.baskom@yandex.ru

engineer of the I category

Россия

Boris Feliksovich Melnikov

Samara State University, Samara

Email: b.melnikov@tltsu.ru

Doctor of Physics and Mathematics, Professor

Россия

Svetlana Valentinovna Pivneva

Togliatti State University, Togliatti

Author for correspondence.
Email: tlt.swetlana@rambler.ru

candidate of pedagogical sciences, Associated Professor, assistant professor of the Department «Higher mathematics and mathematical modeling»

Россия

References

  1. Ma B.M. Materiali yadernikh energeticheskikh ustanovok [Materials of nuclear power plants]. Moscow, Energoatomizdat publ., 1987, 408 p.
  2. Markina N.V., Shimansky G.A. TRANS_MU computer code for computation of transmutant formation kinetics in advanced structural materials for fusion reactors. Journal of nuclear materials, 1999, vol. 271-272, pp. 30–34.
  3. GOST R 8.736-2011. Izmereniya pryamie mnogokratnie. Metodi obrabotki rezultatov izmereniy. Osnovnie polozheniya [Direct multiple determinations. Methods of measuring results processing. Basic statements]. Moscow, Standartinform publ., 2013, 24 p.
  4. Metropolis N., Ulam S. The Monte Carlo Method. Journal of the American Statistical Association, 1949, vol. 44, no. 247, pp. 335–341.
  5. Sobol’ I.M. Metod Monte-Karlo [The Monte Carlo Method]. Moscow, Nauka publ., 1985, 78 p.
  6. Frank-Kamenetsky A.D. Modelirovanie traektoriy neytronov pri raschete reaktorov metodom Monte-Karlo [Modeling of neutrons traces when calculating reactors using Monte-Carlo method]. Moscow, Atomizdat publ., 1978, 96 p.
  7. Kolmogorov A.N., Fomin S.V. Elementi teorii funktsiy i funktsionalnogo analiza [Elements of theory of functions and functional analysis]. 4th ed. Noscow, Nauka publ., 1976, 544 p.
  8. Mendel’ I.D. Klasterniy analiz [Cluster analysis]. Moscow, Finansi i statistika publ., 1988, 176 p.
  9. Grudzevich O.T., Zelenetsky A.V., Ignatyuk A.V., Pashchenko A.B. Nuclear data library for activation and transmutation calculations. Atomic Energy, 1994, vol. 76, no. 2, pp. 127–130.
  10. Lebedev V.B. Modeling of data structure using the methods of trellis theory. Sbornik statey X mezhdunar. nauchno-prakt. konf. “Problemi informatiki v obrazovanii, upravlenii, ekonomike i tekhnike”. Penza, PDZ publ., 2010, pp. 41–45.
  11. Lyuger D.F. Iskusstvenniy intellect: strategii i metodi resheniya slozhnikh problem [Artificial intelligence: strategies and methods of the complex issues solving]. 4th ed. Moscow, Vilyams publ., 2003, 864 p.
  12. Gerasimov A.S., Zaritskaya T.S., Rudik A.P. Spravochnik po obrazovaniyu nuklidov v yadernikh reaktorakh [Reference book on the nuclides production in the nuclear reactors]. Moscow, Energoatomizdat publ., 1989, 574 p.
  13. Fusion Evaluated Nuclear Data Library. URL: www-nds.iaea.org/fendl/index.html.
  14. Belozerova A.R., Pivneva S.V. About one mathematical model the nuclear transmutations problem. Part II. Results of computing experiments. Vektor nauki Tolyattinskogo gosudarstvennogo universiteta, 2013, no. 3, pp. 37–40.
  15. Belozerova A.R., Melnikov B.F. Approach to mathematical simulation of transmutational processes in nuclear power plants. Izvestiya visshikh uchebnikh zavedeniy. Povolzhsky region. Fiziko-matematicheskie nauki, 2014, no. 2, pp. 88–100.
  16. Belozerova A.R., Belozerov S.V. An approach to construction of heuristic algorithms for quality of experimental data by neutron activation analysis measurements. Evristicheskie algoritmi i raspredelennie vychisleniya, 2014, vol. 1, no. 4, pp. 6–23.
  17. PREPRO 2007. URL: www-nds.iaea.org/ndspub/endf/prepro2007.
  18. 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.
  19. Beskorovayniy N.M., ed. Konstruktsionnie materiali yadernikh reaktorov. Chast’ 2. Struktura, svoystva, naznachenie [Structural materials of nuclear reactors. P.2. Structure, properties, application]. Moscow, Atomizdat publ., 1977, 256 p.
  20. Levin V.E. Yadernaya fizika i yadernie reaktori [Nuclear physics and nuclear reactors]. 4th ed. Moscow, Atomizdat publ., 1979, 288 p.

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