快中子堆瞬发超临界的固有安全性  

Inherent Safety of Super-prompt Critical Reactivity of Fast Reactor

作　　者：王洲[1,2] 

机构地区：[1]清华大学热能工程系,北京100084 [2]中国原子能科学研究院,北京102413

出　　处：《核科学与工程》2014年第1期12-15,共4页Nuclear Science and Engineering

摘　　要：本文根据中子动力学结合热力学的分析,指出不论是快堆(快中子堆)还是热堆(压水堆),它们的安全运行都是基于固有和加强双层安全的原理上。随反应性为间隔或斜坡引入方式,而导致瞬发超临界时,在瞬发过程中,快堆达到的最高功率峰值可能很高,但相对其瞬发一代中子寿命来说,两种堆型瞬间放出的能量几乎一样。由这些参数可见,两种堆型的安全标准是一致,而与一代中子寿命无关。与原子弹相比,反应堆与原子弹的基本区别是基于概念设计,而非只取决于瞬发一代中子寿命。On the basis of neutron kinetic and thermodynamic analysis, this paper shows that during the operation of a fast or thermal reactor, their safety assessment necessarily involves both the consideration of feedback effect and control rod reactivity effect and that depending on the insertion reactivity as either steps or ramps during prompt critical excursions, the maximum power burst may be high for the fast reactor but the transient energy release nearly has the same magnitude with respect to the prompt neutron generation lifetimes for both cases. These parameters show that the two reactor types have the same safety level and have no relation to the neutron generation lifetimes. A nuclear reactor is different from atomic bomb mainly in concept design, but not the neutron generation lifetimes.

关 键 词：快中子堆 一代中子寿命 瞬发超临界反应性 最高功率峰尖 能量释放 

分 类 号：TL364.1[核科学技术—核技术及应用]