Extension of the TRANSURANUS burn-up model
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P. Van Uffelen | Wim Haeck | J. van de Laar | Clive T. Walker | C. Walker | W. Haeck | P. V. Uffelen | A. Schubert | A. Schubert | J. V. D. Laar
[1] R. Manzel,et al. On the oxidation state of UO2 nuclear fuel at a burn-up of around 100 MWd/kgHM , 2005 .
[2] M. Betti,et al. The Use of SIMS and SEM for the Characterization of Individual Particles with a Matrix Originating from a Nuclear Weapon , 2007, Microscopy and Microanalysis.
[3] John Gittus. Water reactor fuel element performance computer modelling , 1983 .
[4] K. Lassmann,et al. The radial distribution of plutonium in high burnup UO2 fuels , 1994 .
[5] Wim Haeck,et al. Application of EPMA Data for the Development of the Code Systems TRANSURANUS and ALEPH , 2007, Microscopy and Microanalysis.
[6] Philip R. Page,et al. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology , 2006 .
[7] Yang-Hyun Koo,et al. Cosmos: A computer code to analyze LWR UO2 and MOX fuel up to high burnup , 1999 .
[8] B. Verboomen,et al. An Optimum Approach to Monte Carlo Burnup , 2007 .
[9] H. Zwicky,et al. Radial Plutonium and Fission-product Isotope Profiles in Mixed-oxide Fuel-pins Evaluated By Secondary-ion Mass-spectrometry , 1993 .
[10] Youn Ho Jung,et al. RAPID model to predict radial burnup distribution in LWR UO2 fuel , 2000 .
[11] K. Lassmann,et al. Extension of the TRANSURANUS burnup model to heavy water reactor conditions , 1998 .
[12] D. Papaioannou,et al. On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100 MWd/kgHM , 2006 .
[13] R. Manzel,et al. EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM , 2002 .
[14] Suzuki Motoe. Analysis of high burnup fuel behavior in Halden reactor by FEMAXI-V code , 2000 .
[15] Albert B. Reynolds,et al. Fast breeder reactors , 1981 .
[16] R. J. White,et al. Measurement and Analysis of Fission Gas Release from BNFL's SBR MOX Fuel. , 2001 .
[17] Andrej Trkov,et al. Revisiting the 238U Thermal Capture Cross Section and Gamma-Ray Emission Probabilities from 239Np Decay , 2005 .
[18] T. Matsumura,et al. Effect of inhomogeneity on the level of fission gas and caesium release from OCOM MOX fuel during irradiation , 1996 .
[19] Clive T. Walker,et al. Microstructure of irradiated SBR MOX fuel and its relationship to fission gas release , 2002 .
[20] D. D. Lanning,et al. FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup , 1997 .
[21] S. Lemehov,et al. PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods , 2001 .
[22] K. Lassmann,et al. TRANSURANUS: a fuel rod analysis code ready for use , 1992 .