| 1. | Extrapolating reactor vessel surveillance dosimetry results , e 706
推断反应堆容器监测剂量结果的规程 |
| 2. | The diagram of the reactor vessel internals is used as a reference
将反应堆容器与内部构件的简化图作为参考。 |
| 3. | Certificate holders ' data report for concrete reactor vessels containments
混凝土反应釜容器和外壳的合格证书持有人的数据报告 |
| 4. | Standard guide for in - service annealing of light - water cooled nuclear reactor vessels
轻水冷却核反应堆容器在运转中逐渐冷却的标准指南 |
| 5. | Standard practice for determining neutronexposures for nuclear reactor vessel support structures
核反应堆容器支承结构的中子辐照量测定标准实施规程 |
| 6. | Iid standard guide for application of neutron transport methods for reactor vessel surveillance , e706
反应堆压力容器监视用的中子输运法应用的标准指南. e706 |
| 7. | Standard practice for evaluation of surveillance capsules from light - water moderated nuclear power reactor vessels
评价轻水核电反应堆监视舱的标准实施规程 |
| 8. | Standard practice for design of surveillance programs for light - water moderated nuclear power reactor vessels
轻水冷却核反应堆容器的监督程序设计的标准操作规程 |
| 9. | Iiie standard guide for use of melt wire temperature monitors for reactor vessel surveillance , e 706
使用反应堆堆芯压力容器监督用熔丝温度监视器的标准指南. e 706 |
| 10. | Iif standard guide for predicting radiation - induced transition temperature shift in reactor vessel materials , e706
在反应堆容器材料中预测辐射感应变化导致温度的变化的标准指南, e 706 |
