DOI: 10.55176/2414-1038-2021-3-68-76
Authors & Affiliations
Kurina I.S., Frolova M.Y., Chesnokov E.A., Ryaby V.M., Dvoryashin A.M., Kanunnikov M.Yu.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Kurina I.S. – Leading Researcher, Cand. (Tech. Sci.), Associate Professor. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-86-32; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Frolova M.Yu. – Engineer of the 1st category.
Chesnokov E.A. – Team Leader.
Ryaby V.M. – Head of Laboratory.
Dvoryashin A.M. – Team Leader.
Kanunnikov M.Yu. – First Deputy Director of OIRMiT
Abstract
Density, phase composition, microstructure and thermal conductivity of the U-10 wt. % Zr alloy manufactured by induction melting with subsequent casting into quartz molds and turning to size have been investigated at JSC “SSC RF – IPPE”. For comparison, the density and thermal conductivity of the U-10 wt. % Zr alloy produced by melting followed by extrusion and turning to size were investigated.
To determine the density, a hydrostatic weighing method was used. The average density values of the cast and extruded alloy were respectively 98.8 and 97.5 % of the theoretical density, which was calculated according to the rule of mixtures.
The results of studying the microstructure using a scanning electron microscope are presented. It is shown that the cast alloy U-10 % Zr is a metal matrix in which zirconium-enriched particles of arbitrary shape are distributed. In a metal matrix, the bulk of the volume is occupied by the α-U, and there are also precipitates of the δ-phase in the form of thin plates. A lower value of the microhardness of the alloy is noted in comparison with the data published in the known literature.
The results of measuring the thermal conductivity at temperatures from 100 to 750 °C for the U-10 wt. % Zr alloy obtained by casting and extrusion are presented. The stationary axial heat flux method (or method of plate) was used to measure the thermal conductivity. Alloy samples made in different ways have almost the same thermal conductivity at 200 °C. With an increase in temperature, the discrepancy in thermal conductivity between the samples of the cast and extruded alloy gradually increases, and the thermal conductivity of the extruded alloy turns out to be lower, which is especially noticeable in the temperature range of 600–750 °C. The data obtained are compared with the results of published works. The measured values of the thermal conductivity of the cast alloy U-10 wt. % Zr up to a temperature of 750 °C do not disagree with the literature data. It was found that at a higher temperature, the alloy softens, which, in turn, leads to deformation of the test specimen and an increase in the measurement error when using the axial heat flux method.
Keywords
metal fuel, alloy U-10 wt. % Zr, density, microstructure, phase composition, thermal conductivity, cast alloy, extruded alloy, axial heat flow method
Article Text (PDF, in Russian)
References
- Hofman G.L., Walters L.C. Metallic fast reactor fuels. Materials Science and Technology, 1994, vol. 10A, pp. 1–43.
- Crawford D.C., Porter D.L., Hayes S.L. Fuels for sodium-cooled fast reactors: US perspective. Journal Nuclear Materials, 2007, vol. 371, no. 1, pp. 202–231.
- Burkes D.E., Fielding R.S., Porter D.L., Crawford D.C., Meyer M.K. A US Perspective on Fast Reactor Fabrication Technology and Experience. Part I: Metal Fuels and Assembly Design. Journal Nuclear Materials, 2009, vol. 389, pp. 458–469.
- Steindler M.J., Nelson PA., Johnson C.E. Annual Technical Report for 1986. Report of Argonne National Laboratory, 1987, ANL-87-19, 226 p.
- Kaity S., Banerjee J., Nair M.R., Ravi K., Dash S., Kutty T.R.G., Kumar A., Singh R.P. Microstructural and thermophysical properties of U-6 wt. % Zr alloy for fast reactor application. Journal of Nuclear Materials, 2012, vol. 427, pp. 1–11.
- Nair M.R., Kaity S., Kutty T.R.G., Kumar A., Saify M.T., Jha S.K. Thermal conductivity of U-Zr alloys by transient plane source technique. Proc. Int. Conf. on Characterization and Quality Control of Nuclear Fuels (CQCNF-2012). India, INIS, 2012, vol. 43, no. 17, pp. 46–47.
- Banerjee J., Kaity S., Ravi K., Nair M.R., Saify M.T., Keswani R., Kumar A., Prasad G.J. Out-of-pile thermophysical properties of metallic fuel for fast reactors in India. Proc. Int. Conf. “Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13)”. Paris, 2015, vol. 46, no. 33, p. 10.
- Touloukian Y.S., Powell R.W., Ho C.Y., Klemens P.G. Thermophysical properties of matter – the TPRC data series. Thermal Conductivity – Metallic Elements and Alloys. New York, IFI/Plenum, 1970, vol. 1. 1595 p.
- Touloukian Y.S., Powell R.W., Ho C.Y., Klemens P.G. Experimental Determination of Thermal Conductivity. Thermal Conductivity. New York, IFI/Plenum, 1970, vol. 10, no. 1007/97. Pp. 13–25.
- Cheon J.S., Oh S.-J., Lee B.-O., Lee C.-B. The effect of RE-rich phase on the thermal conductivity of U-Zr-Re alloys. Journal of Nuclear Materials, 2009, vol. 385, pp. 559–562.
- Matsui T., Natsume T., Naito K. Heat capacity measurements of U0.80Zr0.20 and U0.80Mo0.20 alloys from room temperature to 1300 K. Journal of Nuclear Materials, 1989, vol. 167, pp. 152–159.
- Billone M.C., Liu Y.Y., Gruber E.E., Hughes T.H., Kramer J.M. Status of fuel element modeling codes for metallic fuels. Proc. Int. Conf. on Reliable Fuels for Liquid Metal Reactors. Tucson, AZ, American Nuclear Society, 1986, pp. 5–77.
- Kim Y.S., Cho T.W., Sohn D.-S. Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr). Journal of Nuclear Materials, 2014, vol. 445, no. 1–3, pp. 272–280.
- Hales J.D., Williamson R.L., Novascone S.R., Pastore G., Spencer B.W., Stafford D.S., Gamble K.A., Perez D.M., Gardner R.J., Liu W., Galloway J., Matthews C., Unal C., Carlson N. BISON Theory Manual. The Equations Behind Nuclear Fuel Analysis BISON. Release 1.3. Technical Report of Idaho National Laboratory, 2016, INL/EXT-13-29930, 155 p.
- Okuniewski M.A., Tomar V., Bai X., Deo C.S., Beeler B., Zhang Y. Microstructure, Thermal, and Mechanical Properties Relationships in U and U-Zr Alloys – 16-10821. Final Report of Purdue University, 2020, DE-NE0008558, 32 p.
- Kalimullah M. The SAS4A/SASSYS-1 Safety Analysis Code System. SSCOMP: Pre-Transient Characterization of Metallic Fuel Pins. Chapter 10. Report of Argonne National Laboratory, ANL/NE-12/4. Argonne, 2012, 186 p.
- Hofman G.L., Leibovitz L., Kramer J.M., Billone M.C., Koenig J.F. Metallic Fuels Handbook. Report of Argonne National Laboratory, ANL-IFR-29. Argonne, 1985, 184 p.
- Hofman G.L., Billone M.C., Koenig J.F., Kramer J.M., Lambert J.D.B., Leibovitz L., Orechwa Y., Pedersen D.R., Porter D.L., Tsai H., Wright A.E. Metallic Fuels Handbook. Report of Argonne National Laboratory, ANL-NSE-3. Argonne, 2019, 210 p.
- GOST 25281–82 (ST SEV 2287–80). Metod opredeleniya plotnosti formovok [State Standard 25281–82 (ST SEV 2287–80) Method for determining the density of moldings]. Moscow, Standarts Publ., 1982, 12 p.
- Douglas L.P. Density of U-10 wt. % Zr Materials. Report of Idaho National Laboratory, INL/EXT-17-41917. Idaho, 2017.
- Rai A.K., Subramanian R., Hajra R.N., Tripathy H., Rengachari M., Saibaba S. Calorimetric Study of Phase Stability and Phase Transformation in U-xZr (x = 2, 5, 10 Wt Pct) Alloys. Metallurgical and Materials Transactions A, 2015, vol. 46, no. 11, pp. 4986–5001.
- Basak C.B., Prasad G.J., Kamath H.S., Prabhu N. An evaluation of the properties of As-cast U-rich U-Zr alloys. Journal of Alloys and Compounds, 2009, vol. 480, pp. 857–862.
- Kurina I.S., Popov V.V., Rumyantsev V.N., Dvoryashin A.M. Issledovanie svoystv modifitsirovannykh oksidov s anomal'no povyshennoy teploprovodnost'yu [Research of the properties of modified oxides with anomalously increased thermal conductivity]. Perspektivnye materialy – Perspektivnye materialy, 2009, no. 3, pp. 38–45.
- Blamer B.J. Haracterization of uranium metal alloy fuel forms for advanced nuclear reactor applications. Diss. PhD, 2017, Texas A&M University, 264 p.
- Irukuvarghula S., Blamer B., Ahn S., Vogel S.C., Losko A.S., McDeavitt S.M. Texture evolution during annealing of hot extruded U-10 wt. % Zr alloy by in situ neutron diffraction. Journal of Nuclear Materials, 2017, no. 497, pp. 10–15.
- McKeown J., Wall M., Hsiung, Turchi P. Report on Characterization of U-10 wt. % Zr Alloy. Report of Livermore National Laboratory, LLNL-TR-534973. Livermore, 2012, 17 p.
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Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 3, 3:5