2019-3(32)

Operation of nuclear industry facilities

Article Name10.26583/GNS-2019-03-10
Ways to Improve the Coefficient Reproduction of Quick Reactors with Oxide Fuel and Sodium Coolant
AuthorsA.K. Harutyunyan1, S.B. Vygovskiy2, A.G. Khachatryan3
Address

National Research Nuclear University Moscow Engineering Physics Institute (NRNU MEPhI), Kashirskoye shosse, 31, Moscow, Russia 1154091

1ORCID iD: 0000-0003-1281-0791

Publons: Aram Harutyunyan

e-mail: aram5041@outlook.com

2ORCID iD: 0000-0002-9995-1222

  WoS Researcher ID: P-5608-2018

e-mail: vigovskii@mail.ru

3ORCID iD: 0000-0002-1785-5342

  WoS Researcher ID: P-5318-2018

e-mail: artsrun-khachatryan@mail.ru

AbstractThis article presents the results of a numerical study of ways to increase the reproduction rate of fast reactors with oxide fuel and sodium coolant. The purpose of this work is to study and detect fuel or fuel combination with the best technical and economic indicators for the BN-800 reactor facility which will increase not only economic indicators but also the efficiency of the entire pre-reactor cycle. Since over time the problems associated with a decrease in the amount of U235 which leads to an increase in its price and an increase in the amount of accumulated Pu which in the initial time is obtained in the framework of the military industry, worsen throughout the world. But today there is a need to look for ways to compensate for these phenomena with the priority of reliable and safe operation of a nuclear installation from the reprocessing of spent nuclear fuel (spent nuclear fuel) from WWER and RBMK. The paper examines the effects of several important factors on the performance of the reactor and on economic performance. These factors are the use of different fuels and fuel combinations, the geometrical dimensions of the reactor, the distribution of enriched fuel in the core, as well as the change in the specific volume of fuel within the permitted limits.
Keywordsreproduction rate, non-uniformity coefficient, fuel cycle, reactor core
LanguageRussian
References
  1. Larson A. Rapid Advancements for Fast Nuclear Reactors. POWER. URL: https://www.powermag.com/rapid-advancements-for-fast-reactors/?pagenum=1 (the date of circulation: 08/05/2019)
  2. Rachkov V.I., Poplavskiy V.M., Tsibulya A.M., Bagdasarov YU.Ye. Kontseptsiya perspektivnogo energobloka s bystrym natriyevym reaktorom BN-1200 [The Concept of Promising Power Unit with BN-1200 Fast Sodium Reactor]. Atomnaya energiya [Nuclear Energy]. 2010. T. 108, issue 4. P. 202-206 (in Russian).
  3. Uolter A., Reynol'ds A. Reaktory-razmnozhiteli na bystrykh neytronakh [Fast Neutron Breeder Reactors]. Moskva [Moscow]. Energoatomizdat, 1986. 623 р. (in Russian).
  4. Rineyskiy A.A. Inzhiniring energobloka s reaktorom na bystrykh neytronakh BN-800 [Engineering Unit with Fast Neutron Reactor BN-800]. Atomnyye strategi [Atomic strategies]. 2006. № 23. P. 49-60 (in Russian).
  5. Ishkhanov B.S., Stepanov M.Ye., Tret'yakova T.Yu. Reaktory na bystrykh neytronakh [Fast Neutron Reactors]. Yadernaya fizika i chelovek [Nuclear Physics and Human] URL: http://nuclphys.sinp.msu.ru/mfk/mfk09.pdf (date of application: 08.05.2019).
  6. Apse V.A., Shmelev A.N. Ispol'zovaniye programmy TIME26 v kursovom proyektirovanii bystrykh reaktorov i elektroyadernykh ustanovok [The Use of the TIME26 Program in course Design of Fast Reactors and Power Plants]. Moskva [Moscow]. Izd-vo MIFI 2008. 63 p.
    (in Russian).
  7. Leypunskiy A.I. Reaktory na bystrykh neytronakh [Fast Neutron Reactors]. Atomnaya energiya [Nuclear Energy]. 1974. – T 36, issue 5. P. 341-355 (in Russian).
  8. Kalin B.A., Platonov P.A., Chernov I.I., Shtrombakh Ya.I. Yadernyye toplivnyye materialy [Nuclear Fuel Materials]. Moskva [Moscow]: MEPhI Publishing House 2008. T. 6, Part.2. 672 p. (in Russian).
  9. Sinyatkin Ye.Yu, Kuz'min A.V. Teplofizicheskiye svoystva tverdogo dioksida urana v rabochem diapazone temperatur sovremennykh VVER [Thermophysical Properties of Solid Uranium Dioxide in the Working Temperature Range of Modern WWER]. XVII mezhdunarodnaya nauchno-prakticheskaya konferentsiya [XVII International Scientific and Practical Conference]: Sovremennyye tekhnika i tekhnologii [Modern Techniques and Technologies]: materialy mezhdunar. Konf [Materials of the International Conference]. Tomsk, 18-22 April 2011 – Tomsk: Tomskiy politekhnicheskiy universitet [Tomsk Polytechnic University]. 2011. P. 263-264
    (in Russian).
  10. Kannan I. Power Reactors. NPTEL, Mechanical Engineering. – URL: https://nptel.ac.in/
    courses/112101007/1 (the date of circulation: 04/27/2019).
  11. Dement'yev B.A. Yadernyye energeticheskiye reaktory [Nuclear Power Reactors]. Moskva [Moscow]. Energoatomizdat, 1984. 280 p. (in Russian).
  12. Kuzmin A.V., Yurkov M.M. Thermal conductivity coefficient UO2 of theoretical density and regular stoichiometry : Thermophysical Basis of Energy Technologies. MATEC Web of Conferences. Tomsk, Jan. 2017.
Papers89 - 100
URL ArticleURL Article
 Open Article