Zobrazeno 1 - 4
of 4
pro vyhledávání: '"BRUCE MATTHEWS"'
Publikováno v:
Journal of Nuclear Materials. 170:169-177
A volumetric swelling correlation for UN fuel with Nb-1% Zr and PWC-11 cladding materials for application to space nuclear power systems was developed as: ΔV / V (%) = 4.7 × 10 −11 T aV 3.12 Bu 0.83 ρ 0.5 , where T av is the volume averaged fuel
Autor:
R. Bruce Matthews, Richard J. Herbst
Publikováno v:
Nuclear Technology. 63:9-22
Uranium-plutonium carbide offers an improved fuel system for advanced breeder reactors. The high-thermal conductivity and density of carbide fuels permit superior breeding performance and high spec...
Publikováno v:
Journal of Nuclear Materials. 151:318-326
This research compiled and analyzed UN fuel thermal conductivity data covering the temperature range from 10 to 1923 K, and fuel density of 93% to 100% TD and, then developed a thermal conductivity correlation for 100% dense UN fuel: k(W/m K) = 1.37T
Autor:
R. Bruce Matthews, Richard J. Herbst, G. Kocamustafaogullari, S. H. Chan, James M. Wu, Chun-Fa Chuang, N. Scott Cannon, Gary L. Wire, John O. Barner, Richard J. Guenther, Maxwell D. Freshley, Carl E. Crouthamel, William L. Kuhn, Richard D. Peters, Scott A. Simonson, Gerhard V. P. Watzel, Ingolf Auler, Keith F. Dufrane, Michael D. Naughton, G. Romeo, Amos Notea, Yitzhak Segal, Jean-Louis Campan, Gérard Pinard-Legry, Alain J. Vignes, Guy G. Loomis, Rex W. Shumway, Yuji Enokido, Sadamu Yamanouchi, Junji Komatsu, Toshiyuki Itaki, J. V. Sandberg, J. T. Routti, Ansar Parvez, Martin Becker, Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga
Publikováno v:
Nuclear Technology. 63:1-7