Authors & Affiliations
Orlova E.A.1, Kruglov A.B.2, Chuvayev D.V.3, Struchalin P.G.2, Zagrebaev C.A.1, Zhmurin V.G.1
1A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2National Research Nuclear University MEPhI, Moscow, Russia
3Obninsk Institute for Nuclear Power Engineering, Obninsk, Russia
Orlova E.A. – Cand. Sci. (Tech.), Associate Professor, Leading Researcher, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga reg, Russia, 249033. Tel.: (484)399-42-34; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zagrebaev C.A. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Zhmurin V.G. – Leading Enginear, A.I. Leypunsky Institute for Physics and Power Engineering.
Kruglov A.B. – Cand. Sci. (Tech.), Associate Professor, Leading Researcher, National Research Nuclear University MEPhI.
Struchalin P.G. – graduate student, National Research Nuclear University MEPhI.
Chuvayev D.V. – magistr, Obninsk Institute for Nuclear Power Engineering.
Abstract
Decrease in temperature of fuel by means of a heat-conducting sublayer on the basis of lead ensures its reliable functioning at deep burning out, reduces swelling of fuel and gas emission, increa ses radiation firmness of fuel elements and, thus, increases safety of reactor installation.
At research of fuel elements with nitride fuel and a lead liquid metal sublayer under radiation in reactor BOR-60 the problem of compatibility of an sublayer with a cover of fuel elements from steel of a ferritno-martensitny class of brand 16Cr12WMoSiVNbB is found
We offered option of use as heat-conducting sublayer in fuel elements of the lead alloyed by magnesium, zirconium of the sheeting of nitride (carbide) of zirconium, providing spontaneous formation on a surface of steel in an eutectic on the basis of lead with the maintenance of 2,25% mass (0,164 nuclear shares) of magnesium and to 0,2% mass zirconium. Thus self-curing of casual damages of a covering is provided.
Settlement results of distribution of temperature in fuel elements with nitride fuel containing 13% of Pu testifying to decrease in value of the maximum temperature with 1550°C in the center of fuel in of fuel elements with a helium underlayer to 800°C when using as a liquid metal sublayer of a leadmagnesium eutectic are received. Temperature on external and internal surfaces of a cover from steel doesn't exceed 620°C.
Considering that a Pb-2,25% alloy Mg-to 0,2% of Zr causes anticorrosive protection of an internal surface of a cover and the melting temperature lowered in comparison with lead (248°C are relative 327°C for lead), the specified alloy has clear advantages over lead.
Keywords
fuel element, liquid metal sublayer, lead, magnesium, zirconium eutectic, nitrogen, distribution of temperature
Article Text (PDF, in Russian)
References
1. Belyaeva A.V., Krukov F.N., Nikitin O.N. et. al. Osnovnye rezul'taty issledovaniy uran-plutonievogo nitridnogo topliva posle oblucheniya v reaktore BOR-60 [The main results of researches uranium - plutonium nitride fuel after radiation in the reactor the BOR-60]. Trudy mezhdunarodnoy nauchnotekhnicheskoy konferentsii "Innovatsionnye produkty i tekhnologii yadernoy energetiki" [Proc. Int. Sci. Tech. Conf. "Innovative Products and Technologies of Nuclear Power"]. Moscow, 2012, pp. 223-228.
2. Zelensky G.K., Ioltukhovsky A.G., Leontyeva-Smirnov M.V., Meshcherinov I.A., Anuchkin A.M. TVEL reaktora tipa BREST i sposob legirovaniya svintsa dlya teploperedayushchego podsloya TVELA [Fuel element of the BREST reactor and a way of an alloying of lead for a heat-transmitting underlayer of fuel element]. Patent RF, no. 2270486, 2006.
3. Orlov V.V., Leonov V.N., Orlova E.A. Sposob formirovaniya zashchitnogo pokrytiya na poverkhnosti metalla [Method of formation of a sheeting on a metal surface]. Patent RF, no. 2439203, 2012.
4. Orlov V.V., Orlova E.A., Tsikunov V.S., et. al. Formirovanie zashchitnykh nitridnykh po-krytiy na poverkhnosti staley [Formation of protective nitride coverings on a surface steel]. Preprint NIKIETET–08/77 – Preprint NIKIET-ET–08/77. Moscow, 2008.
5. Orlova E.A., Gurbich A.F., Molodtsov S.L., et. al. Formirovanie i issledovanie zashchitnykh pokrytiy, sovmestimykh s nitridnym toplivom, na stalyakh ferritno-martensitnogo klassa [Formation and research of the sheetings compatible to nitride fuel, on the steels of a ferritno-martensitny class]. Atomnaya energiya - Atomic Energy, 2008, vol. 105, no. 5, pp. 269-274.
6. Orlova E.A., Orlov Yu.I., Kruchkov E.A., et. al. Samoorganizuyushcheesya karbonitridnoe pokrytie na stali iz rasplavlennoy evtektiki svinets-magniy [The self-organizing karbonitridny covering on steel from the melted eutectic lead-magnesium]. Obninsk, IPPE Publ., 2013. pp. 233-240.
7. Kramerov A.Ya., Shevelyov Ya.V. Inzhenernye raschety yadernykh reaktorov [Engineering calculations of nuclear reactors]. Moscow, Energoatomizdat Publ., 1980.
8. Kruglov A.B., Kruglov V.B., Kharitonov V.S., Struchalin P.G., Orlova E.A., Zagrebaev S.A., Zhmurin V.G. Teploprovodnost' splavov Pb-Mg v diapazone temperatur 300-650°C [Teploprovodnost of Pb-Mg alloys in the range of temperatures 300-650°C]. Trudy Konf. "Teplomassoperenos i svoystva zhidkikh metallov. Teplofizika-2015" [Proc. Conf. "Heat And Mass Transfer And Properties Of Liquid Metals. Thermal Physics-2015"]. Obninsk, 2015, pp. 28-29.
9. Rogozkin B.D., Bibilashvili Yu.K., Kazennov Yu.I., et al. Predvaritel'noe eksperimental'noe obosnovanie konstruktsii tvela s mononitridnym toplivom i svintsovym podsloem dlya reaktora BREST [Preliminary experimental justification of a design of fuel element with mononitride fuel and a lead underlayer for the reactor BREST]. Trudy konferentsii "Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh" [Proc. Conf. " Heavy liquid metal coolant in nuclear technologies"]. Obninsk, 1998, vol. 2, pp. 458-466.
10. Naumov V.V., Sil-Novitsky A.G., Smirnov V.S., et. al. Trebovaniya k aktivnoy zone reaktorov BREST [Requirements to an active zone of reactors BREST]. Trudy konferentsii "Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh" [Proc. Conf. " Heavy liquid metal coolant in nuclear technologies"]. Obninsk, 1998, vol. 2, pp. 511-520.
11. Rogozkin B.D., Stepennova N.M., Proshkin A.A. Mononitridnoe toplivo dlya bystrykh reaktorov [Mononitride fuel for fast reactors]. Atomnaya energiya - Atomic Energy, 2003, vol. 95, no. 3, pp. 208-221.
12. Bauer A. Nitride Fuels: Properties and Potentials. Journal Reactor Technology, 1972, vol. 15, no. 2, pp. 87.
13. Kirillov P.L., Terentyeva M.I., Deniskina N.B. Teplofizicheskie svoystva materialov yadernoy tekhniki [Thermal properties of materials of nuclear engineering]. Moscow, Izdat Publ., 2007. 360 p.
UDC 621.039.546:621.039.534
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 4, 4:11
