抗核辐射条件的应变计粘贴与防护技术

本文介绍了在重水反应堆中进行应变测量的若干技术成果，主要是较好地解决了用在核辐射条件下，有水流冲刷的环境中应变计的粘贴与防护技术。在具有核辐射的环境中测试，通常选用聚酰亚胺胶作粘结剂。但是这种胶需在高温条件下固化，如果被测构件较大。是无法实现的。经测试筛选出具有防水防辐射性能的常温固化胶，并介绍了可用航空导线替代具有抗辐射性能的铠装电缆在堆内进行测量问题。采用有关措施后，经标定，在核辐射前后应变计灵敏系数相对变化量仅６．６％。经堆内实测证明，所选常温固化胶、测量导线和贴片工艺效果良好。

Analysis of severe core damage accident progression for the heavy water reactor

In this study,the severe accident progression analysis of generic Canadian deuterium uranium reactor 6 was preliminarily provided using an integrated severe accident analysis code.The selected accident sequences were multiple steam generator tube rupture and large break loss-of-coolant accidents because these led to severe core damage with an assumed unavailability for several critical safety systems.The progressions of severe accident included a set of failed safety systems normally operated at full power,and initiative events led to primary heat transport system inventory blow-down or boil off.The core heat-up and melting,steam generator response,fuel channel and calandria vessel failure were analyzed.The results showed that the progression of a severe core damage accident induced by steam generator tube rupture or large break loss-of-coolant accidents in a CANDU reactor was slow due to heat sinks in the calandria vessel and vault.

印度加快核电建设

印度科学家依靠本国技术建造的首座540MW加压重水反应堆（PHWR）已达到临界点。这座核电站位于印度马哈拉施特拉邦的塔拉普尔，它也是印度至今自行设计建造的最大的核动力反应堆。该核反应堆的试运转在技术和管理方面实现了多项突破，反应堆的设计结合了现有加压重水反应堆的所有基本特色，如现有的220MW装置的安全特点，多种快速反应独立关闭系统、高压堆芯紧急冷却系统、双重密封、有冗余多样性等安全目标的辅助控制定、避免常见故障等，都已融入到540MW装置的设计制造中。另外，通过设计创新提高了核电站零部件的国产化。

印度的钍燃料反应堆研发领先

印度最新的下一代核反应堆设计——先进重水反应堆（AHWR）处于研发的最后阶段，该堆的燃料是钍。印度的钍燃料反应堆研发居于世界领先地位。