Suwardi Suwardi


In recent years, a novel class of zirconium alloys having the melting temperature of 990-1160 K has been developed. Based on novel zirconium matrix alloys, high uranium content fuel pin with U-9Mo has been developed according to capillaryimpregnation technique. The pin shows its thermal conductivityranging from 18 to 22 w/m/K that is comparably higher than UO2pellet pin. The paper presents the met-met fabrication and thermal performance analysis of the fuel in typical PWR. Thefabrication consists of mixing UO2 powder or granules and a novel Zr-alloy powder having low melting point, filling the mixture in a cladding tube that one of its end has been plugged, heating the pin to above melting temperature of Zr-alloy for an hour, natural cooling and heat treating at 300 K for ½ hr. The thermal analysis takes into account the pore and temperature distribution and high burn up effect to pellet conductivity. The thermal diffusivity ratio of novel to conventional fuel has been used as correction factor for the novel fuel conductivity. The results show a significant lowering pellet temperature along the radius until 1000 K at the hottest position. The analysis underestimates since the gap conductivity has been treated as decreased by 2 % fission gas released that is not real since the use of lower temperature, and also decreasing thermal conductivity by porosity formation will much lower. The analysis shows that the novel fuel has very good thermal properties which able to pass the barrier of 65 MWD/kg-U, the limit to day commercial fuel. The burn-up extension means less fresh fuel is needed to produce electricity, preserve natural uranium resource, easier fuel handling operational per energy produced.

Full Text:

PDF (Indonesian)


K-K Tae, (1990), Nuclear Fuel Design and Fabrication, in Nuclear Fuel Engineering, KHNP

W.D. Manly, (1956), "Fundamentals of Liquid Metal Corrosion", Corrosion, 12, 46-52.

J. Rest,(1975), "SST: A Computer Code to Predict Fuel Response and Fission Product Release from Light Water Reactor Fuels During Steady-State and Transient Conditions," Trans. Am. Nucl. Soc. 22(1),462-463,


M.G. Andrews, H.R. Freeburn, and S.R. Pati, (1976), "Light Water Reactor Fuel Rod Modeling Code Evaluation, Phase II Topical Report",CENPD-218, Combustion Engineering, Inc., Appendix A, April.

P.E. MacDonald, ed., (1976), "MATPRO: A Handbook of Materials Properties for Use in the Analysis of Light Water Reactor Fuel Rod Behavior", ANCR-1263, NRC-5, Aero jet Nuclear Company, February.

PA-115-75, (1975) "Derivation of a Burnup Dependent Fission Gas Release Model for Use in the PAD Fuel Performance Code", Westinghouse, August.

United States Patent 6881376 (2005).

H.J., Ritzhaupt, et all. (1993), SATURN=FS 1 A computer code for Thermo-mechanical Fuel Rod Analysis, Kernforschungszentrum Karlsruhe

J.S. Tulenko and R.G. Connell, An Innovative Fuel Design Concept for Improved Light Water Reactor Performance and Safety, Technical Report No. DE-F602-92ER75702

http://www. Accessed February 1, 2009

Suwardi, (2006), Influence of Pore Distribution Model on Temperature Prediction of High Burn-up UO2 Fuel, TM. On Economy and Modelling High Burnup Nuclear Fuel, Sofia-Bulgaria, IRNRE-BGS & IAEA, September 2006

Rhee, Young Woo et al., U.S. Patent Application no. 20050261136, (02/02/2005)

J.S. Tulenko and R.G. Connell, An Innovative Fuel Design Concept for Improved Light Water Reactor Performance and Safety, Technical Report No. DE-F602-92ER75702

Gradel, Gerhard; Dorr, Wolfgang, U.S. Patent No. 6808656, (2002-03-27)

A.A.Holden, Dispersion Fuel Element, an AEC Monograph, Gordon and Breach Sci. Pub., New York- London-Paris, 1967.

P. D. Tukkunen, Fabrication of CerMets of Uranium Nitride and Tungsten or Molybdenum from Mixed Powders and from Coated Particles, NASA Technical Note no. xx NASA TN D-5136, April 1969

Suwardi, Thermal Performance Analysis of Novel UO2 Pellet containing Tungsten Matrix for Pressurized Water Reactor, Proc. of the Intern. Conf. on Advances in Nuclear Science and Engineering 2007 © ICANSE 2007, Bandung, Indonesia, November 13 – 14, 2007

ANL, Thermal Conductivity and Thermal Diffusivity of Solid UO2, Argonne National Laboratory


  • There are currently no refbacks.