Authors & Affiliations
Lukyanov D.A.1, Albutova O.I.1, Zverev I.D.2, Shalaev A.V.2, Fadeev I.D.2, Prokoptsov S.I.2, Mikhailenko M.A.3, Guriev S.A.3
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
3 Beloyarsk Nuclear Power Plant, Zarechnyj, Russia
Lukyanov D.A. – Leading Researcher, Cand. Sci. (Tech.), A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-42-88; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Albutova O.I. – Junior Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Zverev I.D. – First category constructor engineer, Afrikantov Experimental Design Bureau for Mechanical Engineering.
Shalaev A.V. – Head Office, Afrikantov Experimental Design Bureau for Mechanical Engineering.
Fadeev I.D. – Head Office, Afrikantov Experimental Design Bureau for Mechanical Engineering.
Prokoptsov S.I. – Design Engineer, Afrikantov Experimental Design Bureau for Mechanical Engineering.
Mikhailenko M.A. – Third category engineer, Beloyarsk Nuclear Power Plant.
Guriev S.A. – Leading engineer, Beloyarsk Nuclear Power Plant.
Abstract
The system of control of tightness of fuel cladding on the activity of fission products of nuclear fuel in the sodium of the primary circuit (NSKGO) of fast neutron reactors of BN type ensures efficient con-trol of the appearance and development of defects of the cladding of fuel elements of type "contact of fuel with coolant" in fast neutron reactors. The technological part of NSKGO of the perspective com-mercial reactor is developed in accordance with the modern conceptual provisions of safety of reactor installations of new generation — the coolant of the primary circuit is not removed from the reactor tank. The report discusses the results of calculation and experimental studies for validation of the performance and effectiveness of NSKGO advanced commercial reactor is obtained on the basis of experience in the development and operation of systems for purification of sodium coolant and control the activity of the nuclides of cesium sorption method.
Keywords
NPP, NSKGO, BN, cladding tightness monitoring, fuel rod
Article Text (PDF, in Russian)
References
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UDC 621.039.526
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, issue 5, 5:11
