Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR

[1]  C. P. Reddy,et al.  An investigation on Unprotected Loss of Flow Accident in Th–Pu metal fuelled 500 MWe fast reactor , 2015 .

[2]  C. P. Reddy,et al.  Criticality safety studies for plutonium–uranium metal fuel pin fabrication facility , 2013 .

[3]  M. Kurata,et al.  Development of Fast Reactor Metal Fuels Containing Minor Actinides , 2011 .

[4]  J. Buongiorno,et al.  A new code for predicting the thermo-mechanical and irradiation behavior of metallic fuels in sodium fast reactors , 2010 .

[5]  P. Mohanakrishnan,et al.  Studies on physics parameters of metal (U–Pu–Zr) fuelled FBR cores , 2008 .

[6]  Takafumi Aoyama,et al.  Distinguished Achievements of a Quarter-Century Operation and a Promising Project Named MK-III in JOYO , 2005 .

[7]  H. S. Kamath,et al.  A perspective on fast reactor fuel cycle in India , 2005 .

[8]  Takeshi Yokoo,et al.  Development and Validation of ALFUS: An Irradiation Behavior Analysis Code for Metallic Fast Reactor Fuels , 1999 .

[9]  L. C. Walters,et al.  Thirty years of fuels and materials information from EBR-II , 1999 .

[10]  Young Cheol Kim,et al.  MACSIS : A metallic fuel performance analysis code for simulating in-reactor behavior under steady-state conditions , 1998 .

[11]  W. Yang,et al.  Average Irradiation Temperature for the Analysis of In-Pile Integral Measurements , 1996 .

[12]  M. Ishida,et al.  Constituent migration model for U-Pu-Zr metallic fast reactor fuel , 1993 .

[13]  Theodore H. Bauer,et al.  In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel , 1995 .

[14]  S. L. Hayes,et al.  Performance of HT9 clad metallic fuel at high temperature , 1992 .

[15]  L. C. Walters,et al.  Irradiation behavior of metallic fast reactor fuels , 1992 .

[16]  C. E. Lahm,et al.  Irradiation experience with HT9-clad metallic fuel , 1991 .

[17]  T. Ogawa,et al.  Demixing of U-Zr alloys under a thermal gradient , 1991 .

[18]  W. Jae,et al.  A comprehensive fission gas release model considering multiple bubble sizes on the grain boundary under steady-state conditions , 1991 .

[19]  Gerard L. Hofman,et al.  Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-ll , 1990 .

[20]  F. E. Panisko,et al.  USER'S GUIDE FOR GAPCON: A COMPUTER PROGRAM TO PREDICT FUEL-TO-CLADDING HEAT TRANSFER COEFFICIENTS IN OXIDE FUEL PINS. , 1972 .

[21]  F. L. Brown,et al.  POSTIRRADIATION EXAMINATION OF U--Pu--Zr FUEL ELEMENTS IRRADIATED IN EBR-II TO 4.5 ATOMIC PERCENT BURNUP. , 1969 .

[22]  P. Shewmon,et al.  Thermal diffusion of substitutional impurities in copper, gold and silver , 1964 .

[23]  C. Harris.  Introduction to Stress Analysis , 1959 .

[24]  R. Brokaw.  Estimating Thermal Conductivities for Nonpolar Gas Mixtures , 1955 .