subcritical reactor

The work presented in this article is focused on the description of the fast-thermal coupled ADS subcritical reactor core and the calculation of the values of K_ ( eff) using the Monte Carlo code MCNP under various parameters of the reactor core.

文章主要是对快热耦合ADS次临界堆芯进行了描述，利用蒙特卡罗代码MCNP模拟计算一系列不同堆芯参数下的K eff值。

It is highly important for us to understand thoroughly critical behaviour of reactor, time-space dependence of neutron flux and physical property during subcritical reactor startup with singular source.

这对于深入了解有奇异源时堆的临界行为和中子通量的时空特性，以及堆在次临界启动时的物理性能，均具有重要的参考价值。

The subcritical reactor physics properties for ADS is studied and analyzed under different external neutron source.

通过对多种外中子源输入的模拟计算，研究分析了ADS系统中次临界堆的物理特性。

~ ( 252) C_f-source-driven neutron noise analysis method is a way of measuring and analyzing the reactivity of reactor or subcritical reactor, which detects subcritical neutron multiplication factor, prompt neutron decay constant, and so on.

~（252）C f源驱动噪声分析法是一种测量、分析反应堆和次临界系统的快速反应性的方法，可作为临界安全的瞬时检测方法。

In this paper, the feasibility of measuring α eigenvalue for a subcritical reactor in the present experiment condition by the pulsed neutron method is discussed.

讨论了在现有源强及测试条件下，用强脉冲源法测量次临界系统中子学时间常数本征值的可行性，并在此基础上对用γ强度谱诊断时间常数进行了研究。

Due to the unique reactor physics characteristics of a subcritical reactor driven by an external neutron source, conventional reactivity measurement methods developed on the base of point reactor model and extensively applied in current critical reactors will be difficult to be directly applied to ADS.

由于外源驱动次临界堆独特的物理特性，使得目前在临界反应堆中广泛应用的基于点堆模型发展起来的传统反应性测量方法很难应用于该系统的次临界度监测。

The Influence on K_ ( eff) by Parameter Change in Subcritical Reactor

次临界堆芯参数变化对K（eff）值的影响

External Steady Neutron Source Transport System for the ADS Subcritical Reactor Physics Research

ADS反应堆物理研究中的稳态外源系统

Through the analysis of the stable neutron density of the subcritical reactor with extraneous neu-tron source, this paper proves that the formula of neutron multiplication with delayed neutron is of great use in the analysis of the subcritical reactor physics.

本文主要内容是通过对有外加中子源反应堆次临界状态下中子密度稳定值的分析，说明考虑缓发中子在内的中子倍增公式对次临界状态的反应堆物理分析是很有用的。