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delayed neutron相关的网络例句

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与 delayed neutron 相关的网络例句 [注:此内容来源于网络,仅供参考]

Based on the comparison of the delayed neutron counter rate of known fission rate with the delayed neutron counter rate of a burst,a method to determine burst total fission number of burst reactor was built.

用长计数器测量已知裂变率的缓发中子计数率,然后用同一探测系统测量脉冲后的缓发中子计数率,探测系统的探测效率、缓发中子份额和缓发中子先驱核半衰期等参数均不变,从而建立起利用脉冲堆脉冲后的缓发中子衰减曲线确定脉冲裂变总数的方法。

Based on this, a resolution was gotten for single-group delayed neutron model.

在此基础上,用修正后的单组模型解析方法进行计算。

Fraction of the total number of neutrons produced from fission, born from delayed neutron

C。 在由分产生之中子总中,自於迟延中子母核的分

Based on the structure and principle of the CEFR delayed neutron detection system, a calculating model of the delayed neutron detection signal was proposed.

根据中国实验快堆缓发中子探测系统的结构特点和探测原理,构建了缓发中子探测系统的计算模型。

B. Fraction of the total number of fast neutrons produced from fission, born from delayed neutron

B。 在由分产生之快中子总中,自於迟延中子母核的分

By using five points thermotechnical model, each point adopts the point-reactor equation which has six delayed neutron groups. To simulate the neutron dynamic states, it was found that it can improve the calculated precision compare to the two points model.

将堆芯在空间上分为5个节点,每节点采用带有六组缓发中子的点堆模型来对其进行动态特性分析,结果表明,对比以前的两节点模型,能够提高一定的计算精度。

The analysis shows that when λ is amended the resolution of single group delayed neutron model is approximately equal to the numerical solution of six groups delayed neutron model, which meets engineering accuracy.

结果表明:采用修正后的单组解析方法计算阶跃正反应性输入的中子密度响应,计算结果与六组的接近,满足工程计算精度要求,同时计算简便,避免了刚性问题,可以实现快速计算。

Considering the fuel salt flow effect of the molten salt reactor, the neutron dynamic model was derived based on the particle conservation equations, and the critical problem was calculated by numerical method under three working conditions to study the flow effect to effective multiplication factor, fast neutron, thermal neutron and delayed neutron precursors distribution.

考虑新概念熔盐堆燃料盐的流动特性,从基本的粒子守恒方程出发,推导了熔盐堆的中子动力学模型,并采用数值方法对3种工况下熔盐堆的临界问题进行计算,考察流动对有效增殖系数、快中子分布、热中子分布及缓发中子先驱核分布的影响。

In the paper, a way of amending λ was introduced to solve the point-reactor neutron kinetics equations so that the numerical solution of single-group delayed neutron model is closed to that of six groups delayed neutron model when a positive step changed reactivity was introduced.

通过修正单组缓发中子先驱核衰变常量λ值,使点堆中子动力学方程单组缓发中子模型在正反应性阶跃输入时的数值计算结果趋近于六组缓发中子模型数值计算结果。

The neutron flux distributions are calculated from the 3D diffosion equations of two energy groups and six delayed neutron precursors by separaing the "time" and "space" variables.

堆芯中子通量分布采用分离变量法对两群六缓发中子组三维扩散方程来实时求解,并考虑慢化剂密度、硼浓度、氙和钐中毒、控制棒位置、燃料和慢化剂温度、燃料燃耗等因素对中子通量分布的影响。

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