Authors & Affiliations
Avvakumov A.V., Mitenkova E.F., Novikov N.V.
Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia
Avvakumov A.V. – Engineer, Nuclear Safety Institute of Russian Academy of Sciences. Contacts: 52, Bolshaya Tulskaya st., Moscow, Russia, 115191. Tel.: +7 (495) 955-23-89; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Mitenkova E.F. – Head of Laboratory, Cand. Sci. (Phys.-Math.), Nuclear Safety Institute of Russian Academy of Sciences.
Novikov N.V. – Senior Researcher, Cand. Sci. (Phys.-Math.), Nuclear Safety Institute of Russian Academy of Sciences.
Abstract
A calculation analysis of the response of ionization chambers located in the concrete protection of the VVER reactor to the neutron flux distribution within the core is a rather complex problem of neutron transport. Here there are the multiple attenuation of neutron flux, leaked from the core and strong an-isotropy of neutron scattering. This task relates to the reactor protection problem, therefore, the accurate models with the Monte Carlo calculation methods are necessary. In this paper, the neutron transport out of the core is modeled using the MCNP5 code in two-dimensional geometry, taking into account the real geometry of the VVER-1000 core, the baffle and location of the neutron flux detectors. As a result of the Monte Carlo calculations, the response weight functions of individual fuel assemblies for several ionization chambers were obtained.
Keywords
nuclear reactor, core, VVER, baffle, lateral ionization chambers, ex-core neutron flux detector, response weight functions, Monte Carlo method
Article Text (PDF, in Russian)
References
1. Vygovskiy S.B., Ryabov N.O., Semenov A.A., Chernov E.V., Bogachek L.N. Fizicheskie i konstruktsionnye osobennosti yadernykh energeticheskikh ustanovok s VVER [Physical and Structural Features of Nuclear Power Plants with VVER]. Moscow, SRNU MEPhI Publ., 2011. 376 p.
2. Avvakumov A.V., Vabishchevich P.N., Vasil'ev A.O., Strizhov V.F. Chislennoe modelirovanie nestatsionarnykh zadach diffuzii neytronov [Numerical Modeling of Neutron Diffusion Problems]. Matematicheskoe modelirovanie - Mathematical Models, 2017, vol. 29, no. 7, pp. 44–62.
3. Ahn J.G., Hwang H.R. Evaluation of Spatial Weighting Functions for Ex-Core Detectors by Adjoint MCNP Calculation. Proc. 4th Brazilian Meeting on Nuclear Applications. Brazil, 1997, vol. 1.
4. Berki T. Calculation of Spatial Weighting Functions for Ex-Core Detectors of VVER-440 Reactors by Monte Carlo Method. Proc. Int. Conf. Nuclear Energy for New Europe 2003. Slovenia, 2003.
5. Farkas G., Slugen V., Hascik J. Calculation of CPNB44 ex-core detector weighting functions for VVER using MCNP5. Proc. 20th Symposium of AER on VVER Reactor Physics and Reactor Safety. Espoo, Finland, 2010.
6. Zheng Y., Lee D., Zhang P., Lee E., Shin H. Comparisons of SN and Monte-Carlo methods in PWR ex-core detector response simulation. Annals of Nuclear Energy, 2017, vol. 101, pp. 139-150.
7. Pecchia M., Vasiliev A., Ferroukhi H., Pautz A. A Methodology for Evaluating Weighting Functions using MCNP and its Application to PWR Ex-Core Analyses. Annals of Nuclear Energy, 2017, vol. 105, pp. 121-132.
8. X-5 Monte Carlo Team. MCNP – A General Monte Carlo N-Particle Transport Code, version 5, April 2003, CCC-710.
9. Mitenkova E.F., Novikov N.V. Tekhnologiya pretsizionnykh raschetov dlya resheniya neytronno-fizicheskikh zadach yadernykh reaktorov [Technology of the Precise Calculations to Solve Nuclear Reactor Neutronic Problems]. Izvestiya RAN - Izvestia RAN, 2004, no. 2, pp. 72–86.
10. 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.
UDC 621.039.514
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 3, 3:4
