Fusion–Fission Hybrid Systems for Transmutation
暂无分享,去创建一个
Antonella L. Costa | Claubia Pereira | Maria Auxiliadora F. Veloso | C. Pereira | Carlos E. Velasquez | Graiciany P. Barros | Graiciany P. Barros | M. A. Veloso | A. Costa | C. E. Velasquez
[1] Timothy Abram,et al. Generation-IV nuclear power: A review of the state of the science , 2008 .
[2] C. Pereira,et al. Neutronic evaluation of the non-proliferating reprocessed nuclear fuels in pressurized water reactors , 1997 .
[3] D. I. Poston,et al. User's manual, version 1.00 for Monteburns, version 3.01 , 1998 .
[4] Antonella L. Costa,et al. Axial Neutron Flux Evaluation in a Tokamak System: a Possible Transmutation Blanket Position for a Fusion–Fission Transmutation System , 2012 .
[5] H. G. Hughes,et al. Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source , 1992 .
[6] W. Stacey. Nuclear Reactor Physics , 2001 .
[7] N. Demir,et al. Neutronic Analysis for Transmutation of Minor Actinides and Long-Lived Fission Products in a Fusion-Driven Transmuter (FDT) , 2006 .
[8] A. G. Croff,et al. User's manual for the ORIGEN2 computer code , 1980 .
[9] E. Schneider,et al. Fusion-Fission Transmutation Scheme-Efficient Destruction of Nuclear Waste , 2012 .
[10] C. Pereira,et al. Fast Accelerator Driven Subcritical System for Energy Production Using Burned Fuel , 2012 .
[11] C. Pereira,et al. Layer thickness evaluation for transuranic transmutation in a fusion–fission system , 2015 .
[12] C. Pereira,et al. Modelling effects on axial neutron flux in a Tokamak device , 2015 .
[13] J. F. Briesmeister. MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .
[14] W. Stacey. Tokamak D–T fusion neutron source requirements for closing the nuclear fuel cycle , 2007 .
[15] Kevin James Kramer. Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System , 2010 .
[16] Antonella L. Costa,et al. A Neutronic Evaluation of Reprocess Fuel and Depletion Study of VHTR Using MCNPX and WIMSD5 Code , 2012 .
[17] Yican Wu,et al. CAD-based interface programs for fusion neutron transport simulation , 2009 .
[18] P. Pereslavtsev,et al. The EU Power Plant Conceptual Study - Neutronic Design Analyses for Near Term and Advanced Reactor Models , 2003 .