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作 者:崔军 李爽 马小雅 陈超 陈晨晨 CUI Jun;LI Shuang;MA Xiaoya;CHEN Chao;CHEN Chenchen(China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen of Guangdong Prov.518031,China)
出 处:《核科学与工程》2024年第2期266-273,共8页Nuclear Science and Engineering
摘 要:随着反应堆的发展,核反应堆设计中的燃料元件趋于多样化。十字螺旋燃料元件便是其中一种,相较于传统的压水堆燃料元件,螺旋状结构元件能够在保证强换热能力的同时维持运行工况下的材料强度和结构完整性,从而提高反应堆安全性和经济性。为了更好描述粒子在燃料组件中的行为,就需对粒子输运方程进行求解。常见求解粒子输运方程方法有确定论和蒙特卡罗方法。相较于确定论方法,蒙特卡罗方法基本可表述任意形状几何。但在目前常见的蒙特卡罗程序中,均未发现有关螺旋曲面几何形状的研究。因此开发了蒙特卡罗程序中螺旋曲面的相关描述方法,并且提出了两种距离求解方法:逼近法和逼近法优化-固定步长调节策略。通过仿真实验比较,发现后者可有效提高计算效率。With the development of reactor,the fuel elements in nuclear reactor design tend to be diversified.Spiral cross fuel elements are one of them.Compared with fuel elements of the traditional pressurized water reactor,the helical cross structure element can enhance the heat transfer capacity while maintaining the material strength and structural integrity under operating conditions[1],thereby greatly improving the safety and economy of the reactor.In order to describe the distribution of neutrons in different regions of the reactor,it is necessary to solve the neutron transport equation.Common methods for solving the neutron transport equation include the deterministic method and the Monte Carlo method.Compared with the deterministic method,the Monte Carlo method use fewer approximations,and the Monte Carlo method can basically describe arbitrary geometric shapes.For the cross-spiral fuel element,the cross-spiral geometry unable to be effectively described in these common Monte Carlo programs.A description method of the helical surface was developed in a Monte Carlo program.And two different solutions are proposed to solve the distance between the neutron and the thread surface,which are the approximation method and the approximation method optimization-fixed step adjustment strategy.Through comparison of simulation experiments,it is found that the latter can effectively improve the calculation efficiency.
分 类 号:TL2[核科学技术—核燃料循环与材料]
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