反应堆轴向功率不均匀系数快速算法

本文提出了用于反应堆运行现场安全校核的反应堆轴向功率不均匀系数的快速算法,导出了轴向功率不均匀系数的快速计算式。     

失流事故冷却剂流量下滑的统一表达式

导出了压水堆失流事故下冷却剂流量下滑的统一表达式,作了实例计算,并对结果进行了讨论。     

新的中子密度方程

采用去耦合法,在未作任何假定的条件下,导出了一个新的点堆中子密度方程.该方程与老的中子密度方程相比,其精度和应用范围都有很大的提高.     

有外中子源时点堆中子动力学方程组的精确解

采用去耦合法,在未作任何假定的条件下,导出了点堆中子动力方程组的精确解。此解可通用于反应堆启动,次临界、缓发超临界,一直到瞬发超临界。此解计算精度高,可用于要求计算精度较高的定量分析,计算工作量小,可用手算。对于反应堆现场运行监督性快速估计的计算,尤为适宜。     

对有外加中子源时反应堆中子密度稳定值的分析

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。     

反应堆控制棒驱动线故障分析

本文分析了反应堆控制棒驱动线几种典型故障发生的原因和机理,并提出了消除故障的改进措施。     

核反应堆运行中安全校核快速计算方法

本文根据潜艇核动力装置运行管理的需要,提出了一个供核反应堆运行中安全校核使用的快速计算方法。     

RUSSIAN NAVAL NUCLEAR FUEL AND REACTORS

Russian naval nuclear fuel and reactors pose both proliferation and environmental threats, ranging from the possible theft of highly enriched uranium fuel to the radioactive contamination of the environment, whether due to accident, neglect, or sabotage. Current conditions at Russian naval bases, together with a history of accidents and incidents involving Russia's nuclear fleet, make a convincing case for the large-scale assistance that the G8 is now providing to improve the safety and security of Russian naval reactors and fuel. However, virtually no data has been released to allow accurate, reliable, and independent analysis of reactor and fuel properties, risking misguided international efforts to assist in the areas of nuclear cleanup, nonproliferation, and security. This article identifies and assesses relevant properties and developments related to reactor and fuel design, provides a comprehensive presentation of Russian nuclear naval technologies, and examines technological trends in the context of proliferation and environmental security.