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DRAGON&DONJON组件-堆芯“两步法”程序通过合理简化,理论可适用于任何堆芯与工况。使用蒙特卡罗方法 RMC(Reactor Monte Carlo code)、MCNP(Monte Carlo Neutron Particle transport code)程序验证DRA&DON程序是否能够承担快/热谱型熔盐堆(Molten Salt Reactor,MSR)焚烧TRU、Th U燃料燃耗计算。选出熔盐增殖堆(Molten Salt Breeder Reactor,MSBR)与熔盐锕系元素再循环和嬗变堆(Molten Salt Advanced Reactor Transmuter,MOSART)堆型进行比较,同时分别利用RMC程序验证DRAGON程序组件燃耗计算的准确性,利用MCNP程序验证DRAGON程序组件均匀化方法以及DONJON程序截面调用和程序全堆扩散的准确性。结果表明,组件燃耗计算中,TRU和Th U燃料满足燃耗计算要求;堆芯临界计算中,快/热谱堆芯计算误差均小于0.001。证明DRA&DON程序可以胜任快、热谱型MSR焚烧TRU、Th U燃料的物理计算任务。
DRAGON & DONJON COMPONENTS - CORE “Two-Step Method ” The procedure is simplified by reason and the theory is applicable to any core and working condition. The Reactor Monte Carlo code (MCMC) and MCNP (Monte Carlo Neutron Particle transport code) programs were used to verify whether the DRA & DON program can be used to incinerate the TRU and ThU fuel for Molten Salt Reactor (MSR) Fuel consumption calculation. Selected Molten Salt Breeder Reactor (MSBR) and Molten Salt Advanced Reactor Transmuter (MOSART) heap type comparison, at the same time, respectively, using the RMC program to verify DRAGON program components burnup The accuracy of the calculation, the use of MCNP program to verify DRAGON program component homogenization method as well as DONJON program cross-section call and the accuracy of the entire program diffusion. The results show that the TRU and Th U fuels meet the fuel consumption calculation requirements in the component fuel burn calculation. The calculation errors of the fast / thermal core are less than 0.001 in the core critical calculation. Prove that the DRA & DON program is capable of performing physics calculations of fast, thermo-spectral MSR incineration of TRU and ThU fuels.