350 rub
Journal Information-measuring and Control Systems №6 for 2013 г.
Article in number:
Nuclear reactor-s neutron flux modeling application in case of technological characteristics random perturbations
Authors:
A.M. Zagrebayev
Abstract:
In this paper the mathematical model and application for nuclear reactor-s neutron flux statistical investigation are described. The goal for developing the application was verification of the possibility to determine the significant parameters for accident-free nuclear reactor running via neutron flux statistical characteristics in passive experiment. As mathematical model authors use correlated equation of reactor neutron physics with fluctuating absorption cross-section, thermal physics and control equations. Mathematical model numerical realization in application uses finite-difference implicit method. The application can be divided into four parts according to functionality: calculation, input, output and statistical processing. In the application it is possible to build the model dynamically i. e. the user can choose witch feedbacks (including control system) should be included into calculation. Also user can set output characteristics and feedback parameters, such as constants, reactivity coefficients structure and values. Numerical calculations proved that the application correctly represent physical processes in nuclear reactor and can be used for statistical researches.
Pages: 65-72
References

 

  1. Vejjnberg A., Vigner E.Fizicheskaja teorija jadernykh reaktorov: Per. s angl. / Pod red. JA.V. SHeveleva. M.: Izd-vo inostr. lit. 1961.
  2. Adamov E. O., Orlov V. V., Gabaraev B. A., Filin A. I. dr. Innovacionnyjj proekt AEHS s reaktorom BREST i pristancionnym toplivnym ciklom dlja ploshhadki Belojarskojj AEHS // Atomnaja ehnergetika. Sostojanie i perspektivy: Materialy 3-jj nauchno-tekhnich. konf. Minatoma Rossii. Moskva, 5 ijunja 2002 g. S. 85 - 107.
  3. Krajushkin A.V., Kubarev A.V. Programma STEPAN-S dlja rascheta kharakteristik jadernojj bezopasnosti. V sb. «Vnutrennjaja bezopasnost jadernykh ehnergeticheskikh ustanovok». M.: CNIIatominform. 1991. s. 228, 229.
  4. Feynman R. P., F. De Hoffmann, and R. Serber. Dispersion of the Neutron Enlission in U-235 Fission. // Journal of Nuclear Energy. 1956. № 3. P. 64
  5. Pal L. On the Theory of Stochastic Processes in Nuclear Reactors. // NuovoCimento (supplement). 1958. № 7. P. 25.
  6. Pal L. «Statistical Fluctuations of Neutron Multiplication». Geneva Conference. 1958. V. 16, 687, P. 1710.
  7. Urig R. Statisticheskie metody v fizike jadernykh reaktorov. M.: Atomizdat. 1974.
  8. Gohn G.E. A Simplified Theory of Pile Noise. // Nuclear Science and Engineering. 1960. V. 7. № 5.P. 472.
  9. Sheff J.R., Albrecht R.W. The Space Dependence of Reactor Noise. // Nuclear Science and Engineering. 1966. V. 24. № 3.P. 246.
  10. Sheff J.R., Albrecht R.W. The Space Dependence of Reactor Noise. // Nuclear Science and Engineering. 1966. V. 26. № 2. P. 207.
  11. Herr J.D., Thomas J.R. Noise analysis for monitoring the moderator tem-perature coefficient of pressurized water reactors. // Nuclear Science and Engineering. 1991. V. 108. P. 341 - 346.
  12. Housiadas C., Antonopoulos-Domis M. The effect of fuel temperature on the estimation of the moderator coefficient in PWRs. // Annals of Nuclear Energy. 1999. V. 26. P. 1395 - 1405.
  13. Kostic L.J., Runkel J., Stegemann D.Thermohydraulics surveillance of pressurized water reactors by experimental and theoretical investigations of the low frequency noise field // Progress in Nuclear Energy. 1988. V. 21. P. 421 - 430.
  14. Kostic L. Monitoring of the temperature reactivity coefficient at the PWR nuclear power plant // Annals of Nuclear Energy. 1997. V. 24. P. 55 - 64.
  15. Laggiard E., Runkel J. Evaluation of the moderator temperature coefficient of reactivity in a PWR by means of noise analysis // Annals of Nuclear Energy. 1997. V. 24. P. 411 - 417.
  16. Laggiard E., Runkel J. Noise analysis estimation of the moderator temperature coefficient for a PWR fuel cycle // Annals of Nuclear Energy. 1999. V. 26. P. 149 - 156.
  17. Pazsit I. Two-phase flow identification by correlation technique. // Annals of Nuclear Energy. 1986. V. 13. P. 37 - 41.
  18. Shieh D.J., Upadhyaya B.R., Sweeney F.J. Application of noise analysis technique for monitoring the moderator temperature coefficient of reactivity in pressurized water reactors. // Nuclear Science and Engineering. 1987. V. 95. P. 14 - 21.
  19. Sweeney F.J. In-core coolant velocity measurements in a pressurized water reactor using temperature-neutron noise cross-correlation. // Transactions of the American Nuclear Society. 1984. V. 46. P. 736 - 738.
  20. Thomas J.R., Herr J.D., Wood D.S. Noise analysis method for monitoring the moderator temperature coefficient of pressurized water reactors. I. Theory. // Nuclear Science and Engineering. 1991. V. 108. P. 331 - 340.
  21. Upadhyaya B.R., Shieh D.J., Sweeney F.J., Glockler O. Analysis of in-core dynamics in pressurized water reactors with application to parameter monitoring. Progress in Nuclear Energy. 1988. V. 21. P. 261 - 269.
  22. Williams M.M.R. The effect of random material density on reactor criticality // Atomkernenergie. 1973. V. 22. P. 248 - 250.
  23. Voroncov B.A., Emeljanov I.JA., Podlazov L.N. i dr. Voprosy diagnostiki fizicheskikh kharakteristik RBMK po nejjtronnym shumam. // Atomnaja ehnergija. 1980. T. 48. Vyp. 3. S. 145 - 48.
  24. A.V. Stepanov Srednjaja plotnost potoka nejjtronov v neodnorodnykh sredakh, NeutrjnThermalizationandReactjrSpectra,  International atomic energy agency. Vienna., 1968. V. 1. P. 193-222.
  25. Galanin A.D. Teorija vozmushhenijj dlja uravnenija s odnojj gruppojj nejjtronov // Atomnaja ehnergija. 1986. T. 60. Vyp. 4. S. 267 - 273.
  26. Karpov V.A., Nazarjan V.G., Postnikov V.V. Issledovanie sluchajjnojj sostavljajushhejj raspredelenija teplovydelenija v jadernom reaktore. // Atomnaja ehnergija. 1976. T. 40. Vyp. 6. S. 456 - 460.
  27. Filipchuk E.V., Potapenko P.T., Postnikov V.V. Upravlenie nejjtronnym polem jadernogo reaktora. M.: EHnergoizdat, 1981.
  28. Gorjunov V.K. Prostranstvennye fljuktuacii raspredelenija nejjtronov i moshhnosti v kriticheskom reaktore. // M.: Atomnaja ehnergija. 1978. T. 44. Vyp. 4. S. 357 - 359.
  29. Gorjunov V.K.Perekosy polja nejjtronov v reaktorakh pri sluchajjno raspredelennykh vozmushhenijakh makrosechenijj // M.: Atomnaja ehnergija. 1980. T. 49. Vyp. 5. S. 321 - 323.
  30. Gomin E.A., Gorodkov S.S. O nekotorykh svojjstvakh fljuktuacijj nejjtronnogo polja v jadernom reaktore // M.: Atomnaja ehnergija. 1979. T. 46. Vyp. 3. S. 187 - 188.
  31. Dollezhal N.A., Emeljanov I.JA. Kanalnyjj jadernyjj ehnergeticheskijj reaktor. M.: Atomizdat. 1980.
  32. Zagrebaev A.M., Nasonova V.A. Verojatnostnye kharakteristiki plotnosti potoka nejjtronov v jadernom reaktore pri sluchajjnykh vozmushhenijakh v svojjstvakh sredy. Izv. vyssh. uchebn. zav. JAdernaja ehnergetika. 2009. № 4. S. 71 - 78.
  33. Zagrebaev A.M., Nasonova V.A., Ovsjannikova N.V. Matematicheskoe modelirovanie jadernogo reaktora pri sluchajjnykh vozmushhenijakh tekhnologicheskikh parametrov. Monografija. M.: NIJAU MIFI. 2011. 180 s.
  34. Zagrebaev A.M., Nasonova V.A. Issledovanija statisticheskikh kharakteristik plotnosti potoka nejjtronov pri sluchajjnykh vozmushhenijakh v svojjstvakh sredy. Estestvennye i tekhnicheskie nauki. 2010. № 6. S. 562 - 564.
  35. Zagrebaev A. M., Nasonova V. A., Ovsjannikova N. V. Statisticheskie issledovanija plotnosti potoka nejjtronov v jadernom reaktore pri sluchajjnykh vozmushhenijakh svojjstv sredy. M.: Atomnaja ehnergija. № 2. T. 111. Avgust 2011. C. 88 - 92.
  36. Zagrebaev A.M. Ocenka verojatnosti obrazovanija lokalnykh nadkriticheskikh zon pri sluchajjnykh vozmushhenijakh svojjstv sredy. // Algoritmy obrabotki informacii v slozhnykh sistemakh. M.: EHnergoatomizdat. 1991.
  37. Zagrebaev A.M.Verojatnost obrazovanija lokalnykh nadkriticheskikh zon pri sluchajjnykh vozmushhenijakh materialnogo parametra sredy. // Nejjtronno-fizicheskie problemy bezopasnosti jaderno-ehnergeticheskikh ustanovok. Tezisy dokl. VI Vsesojuznogo seminara po problemam fiziki reaktorov. Moskva, 4 - 8 sentjabrja. 1989 g. CNII ATOMINFORM.
  38. Zagrebaev A.M.Ob ocenke verojatnosti vybrosa izbytka koehfficienta razmnozhenija nejjtronov v fazovom obeme Trudy KH Mezhdunar. nauchno-tekhn. seminara «Sovremennye tekhnologii v zadachakh upravlenija, avtomatizacii i obrabotki informacii». 2001.
  39. Zagrebaev A.M.O svjazi fizicheskikh i statisticheskikh kharakteristik polja nejjtronov pri sluchajjnykh vozmushhenijakh svojjstv sredy. // Inzhenernaja fizika. 2005. № 4. S. 7 - 11.
  40. Zagrebaev A.M., Kozmin L.A., Krajjko M.A. Matematicheskoe obespechenie dlja opredelenija postojannojj vremeni grafitovojj kladki reaktora RBMK-1000 v passivnom ehksperimente, Trudy KHIII Mezhdunar. nauchno-tekhn. seminara «Sovremennye tekhnologii v zadachakh upravlenija, avtomatiki i obrabotki informacii». M.: Izd-vo MGU. 2004.