Abstract
As a part of the DUPIC (direct use of spent PWR fuel in CANDU reactors) fuel development program, the thermal expansion of simulated spent fuel pellets with dissolved fission products has been studied by using a thermo-mechanical analyzer (TMA) in the temperature range from 298 K to 1773 K to investigate the effects of fission products forming solid solutions in a UO2 matrix on the thermal expansions. Simulated fuels with an equivalent burn-up of (30 to 120) GWd/tU were used in this study. The linear thermal expansions of the simulated fuel pellets were higher than that of UO2, and the difference between these fuel pellets and UO2 increased monotonically with temperature. For the temperature range from 298 K to 1773 K, the values of the average linear thermal expansion coefficients for UO2 and simulated fuels with an equivalent burn-up of (30, 60, and 120) GWd/tU are 1.19 × 10−5 K−1, 1.22 × 10−5 K−1, 1.26 × 10−5 K−1, and 1.32 × 10−5 K−1, respectively.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
I.J. Hastings, P.G. Boczar, C.J. Allan, M. Gacesa, in Proceedings of Sixth KAIF/KNS Annual Conference, Seoul, Korea (1991)
J.S. Lee, K.C. Song, M.S. Yang, K.S. Chun, B.W. Rhee, J.S. Hong, H.S. Park, C.S. Rim, in Proceedings of International Conference on Future Nuclear Systems: Emerging Fuel Cycles and Waste Disposal Options Global ‘93, Seattle, Washington (1993)
Gronvold F.: J. Inorg. Nucl. Chem. 1, 357 (1955)
Baldock P.J., Spindler W.E., Baker T.W.: J. Nucl. Mater. 18, 305 (1966)
Albinati A.: Acta Crystallogr. A 36, 265 (1980)
Hutchings M.T.: J. Chem. Soc. Faraday Trans. 2, 1083 (1987)
Momin A.C., Mirza E.B., Mathews M.D.: J. Nucl. Mater. 185, 308 (1991)
Yamashita T., Nitani N., Tsuji T., Inagaki H.: J. Nucl. Mater. 245, 72 (1997)
Yamashita T., Nitani N., Tsuji T., Kato T.: J. Nucl. Mater. 247, 90 (1997)
Tyagi A.K., Mathews M.D.: J. Nucl. Mater. 278, 123 (2000)
Kang K.H., Ryu H.J., Song K.C., Yang M.S.: J. Nucl. Mater. 301, 242 (2002)
Tokar M., Nutt A.W., Keenan T.K.: Nucl. Technol. 17, 147 (1973)
Lorenzelli R., EL Sayed Ali M.: J. Nucl. Mater. 68, 100 (1977)
Kang K.H., Song K.C., Yang M.S., Lee S.H., Ko J.B., Kim S.W.: Int. J. Thermophys 27, 161 (2006)
Martin D.G.: J. Nucl. Mater. 152, 94 (1988)
M.J. Bell, ORIGEN-The ORNL Isotope Generation and Depletion Code, ORNL-TM4397 (1973)
Kang K.H., Song K.C., Moon J.S., Park H.S., Yang M.S.: Met. Mater.-Korea 6, 583 (2000)
Y.S. Touloukian, Thermophysical Properties of Materials, vol. 12 (IFI/Plenum, New York, 1977)
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Kang, K.H., Na, S.H., Park, C.J. et al. Thermal Expansion of Simulated Fuels with Dissolved Fission Products in a UO2 Matrix. Int J Thermophys 30, 1386–1395 (2009). https://doi.org/10.1007/s10765-009-0588-0
Received:
Accepted:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10765-009-0588-0