References
- ANS Meeting A Decade of Advances in Metallic Fuels B. R. Seidel(et al.)
- Proceedings of ICONE 5 Development Status of MACSIS Code for Simulating the In-Reactor Behavior of Metallic Fuel W. Hwang;C. Nam;J. S. Yim;Y. C. Kim;M. Cho
- Progress in Nuclear Energy v.31 Metallic Fast Reactor Fuels G. L. Hofman;L. C. Walters;T. H. Bauer
- ANL-7602 Postirradiation Examination of U-Pu-Zr Fuel Elments Irradiated in EBR-Ⅱ to 4.5 Atomic Percent Burnup F. Murphy;W. N. Beck;F. L. Brown;B. J. Koprowski;L. A. Neimark
- Metallurgical Transactions v.21A Fuel Stages of U-Pu-Zr Irradiation D. L. Porter;C. E. Lahm;R. G. Pahl
- Nuclear Technology v.110 In-Pile Measurements of the Thermal Conductivity of Irradiated Metallic Fuel T. H. Bauer;J. W. Holland
- J. of the Less-Common Metals v.175 Demixing of U-Zr Alloys Under a Thermal Gradient T. Ogawa;T. Iwai;M. Kurata
- Nuclear Technology v.104 Constituent Migration Model for U-Pu-Zr Metallic Fast Reactor Fuel M. Ishida;T. Ogata;M. Kinoshita
- J. of Nuclear Materials v.227 Temperature Gradient Driven Constituent Redistribution in U-Zr Alloys G. L. Hofman;S. L. Hayes;M. C. Petri
- Nuclear Technology v.115 Average Irradiation Temperature for the Analysis of In-Pile Integral Measurements A. M. Yacout;W. S. Yang;G. L. Hofman;Y. Orechwa
- Diffusion in Solids P. G. Shewmon
- Acta Metallurgica v.12 Thermal Diffusion of Substitutional Impurities in Copper, Gold and Silver D. Jaffe;P. G. Shewmon
- Metallurgical Transactions v.21A A Study of the Thermotransport Behavior of Cobalt in Thorium S. C. Axtell;O. N. Carlson
- Nuclear Science and Engineering v.49 A Numerical Calculation of the Redistribution of an Interstitial Solute in a Thermal Gradient G. P. Marino
- Proc. ANS Conf. Reliable Fuels for LMRs Status of Fuel Element Modeling Codes for Metallic Fuels M. C. Billon;Y. Y. Liu;E. E. Gruber;T. H. Hughes;J. M. Kramer
- ANL-7323 Thermophysical Properties of Sodium G. H. Golden;J. D. Tokar
- J. of Nuclear Materials Analysis of Constituent Redistribution in γ U-Pu-Zr Alloys under a Temperature Gradient Y. H. Sohn;M. A. Dayananda;G. L. Hofman;R. V. Strain;S. L. Hayes
- ANL-7155 Compatibility of U-Pu-Zr and U-Pu-Ti Alloys with Potential Cladding Materials C. M. Walter;L. R. Kelman;S. T. Zegler
- Proc. ANS Int. Conf. on Reliable Fuels for LMRs Recent Irradiation Test of Uranium-Plutonium-Zirconium Metal Fuel Elements P. G. Pahl;C. E. Lahm;R. Villareal;W. N. Beck;G. L. Hofman
- Liquid Sodium Intrusion into Porous U-10Zr Fuel Alloy by Differential Capillarity W. Liu;A. A. Solomon