基于三代压水堆的中国核燃料循环模式仿真研究

Simulation Study of Nuclear Fuel Cycle Mode Based on Third Generation PWR in China

根据国务院出台的《核电安全规划(2011–2020年)》和《核电中长期发展规划(2011–2020年)》和中国工程物理研究院的《中国能源中长期(2030、2050)发展战略研究》及"十三五"规划,以目前主要已运M310堆型和三代核电"华龙一号"、AP1000,CAP1400堆型为主,在MATLAB仿真环境下采用"一次通过"模式分析2050年前我国核燃料循环现状和未来核燃料循环需求,定量的计算仿真出压水堆核电站所需的铀资源、分离功、乏燃料、Pu和次要锕系元素的产生量,计算结果可作为我国核燃料发展战略的重要依据,加快建立闭式核燃料循环模式。

Based on the State Council 2012 ＂Nuclear Safety Plan （2011-2020）＂ and ＂Nuclear Medium and Long-term Development Plan（2011-2020）＂ , the report of＂the research on China energy medium and long-term（2030, 2050） development strategy＂ of China Academy of Engineering Physics and ＂Chinese 13th Five-Year Plan ＂ combined the primary of operating M310 type reactors and the third generation HPR1000, AP1000, CAP1400, and the current and future P WR nuclear fuel cycle mode was studied under MATLAB simulation environment employing ＂once through＂ mode. The demand of natural uranium resource, separate works, the amount of spent fuel, plutonium, also minor actinides arising following the accumulative PWR nuclear reactors were calculated. Simulation result can be made as a reference for China fuel cycle development strategy, which speeds up to establish closed fuel cycle way.