论文标题
使用GEANT4和MCNPX，核工程和设计的中子通量和同位素转化率的计算
Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX, Nuclear Engineering and Design
论文作者
论文摘要
使用模拟程序MCNPX（Waters，2002）和Geant4（Agostinelli，2003）对Myrrha Ads反应堆进行了中性货币计算。通常考虑用于ADS系统的thor，这是使用已详细开发的反应堆设计对基于or的燃料的可能性的首次评估。它还将广泛使用的Geant4程序的应用扩展到Myrrha和Thorium的几何形状。考虑到标准的MOX燃料和可能的232/MOX启动器，考虑了渐近232/233U混合物。中子通量和光谱是在核心的几个区域计算的：燃料电池，IPS细胞和两个（MO和AC）同位素生产细胞。然后将这些用于简单计算燃料演化和焚化次要actacinide废物的潜力。这两个程序的结果同意并互相支持，并表明tho燃料是可行的，具有良好的进化/育种特性，尽管它不会在大规模上进行大规模进行，但次要的Actinide焚化将是可以证明的。
Neutronics calculations have been performed of the MYRRHA ADS Reactor with a thorium-based fuel mixture, using the simulation programs MCNPX (Waters, 2002) and Geant4 (Agostinelli, 2003). Thorium is often considered for ADS systems, and this is the first evaluation of the possibilities for thorium based fuels using a reactor design which has been developed in detail. It also extends the application of the widely-used Geant4 program to the geometry of MYRRHA and to thorium. An asymptotic 232Th/233U mixture is considered, together with the standard MOX fuel and a possible 232Th/MOX starter. Neutron fluxes and spectra are calculated at several regions in the core: fuel cells, IPS cells and the two (Mo and Ac) isotope production cells. These are then used for simple calculations of the fuel evolution and of the potential for the incineration of minor actinide waste. Results from the two programs agree and support each other and show that the thorium fuel is viable, and has good evolution/breeding properties, and that minor actinide incineration, though it will not take place on a significant scale, will be demonstrable.
