月桂酰肌氨酸钠搭建阿尔法凝胶的方法研究及结构表征

阿尔法凝胶作为一种特殊的液晶结构，能够在清洁或调理皮肤的过程中给皮肤毛发提供更好的湿润感和调理性。由于阿尔法凝胶结构的搭建传统方法需要不少于14个碳原子的烷基表面活性剂，其实际应用一直受到限制。提供了一种由月桂酰肌氨酸钠作为烷基碳链为12个碳原子的氨基酸型表面活性剂搭建阿尔法凝胶的方法，并对其产物进行结构表征和分析。     

仪器仪表产品脉冲耐压试验要求和保护器件的选择

仪器仪表产品的脉冲耐压试验是产品型式试验、例行试验中的基本内容。通过对GB4793.1标准的整理,归纳了仪器仪表产品的脉冲耐压试验要求。通过对试验方法和设备特性的梳理,总结了特性参数,并介绍了应对脉冲耐压试验可采取的保护器件的类别及选用方法。     

压水堆核电厂堆外源量程探测器计数率分析

压水堆核电厂启动过程中，次级中子源为堆外源量程探测器提供本底计数率，避免测量盲区，确保反应堆安全启动。但次级中子源的引入会为核电厂带来较大的经济和环境负担，同时也需承受次级中子源破损等带来的风险。为此，可使用受辐照燃料组件的自发裂变中子源进行替代，即无源启动方式。通过研究堆外源量程探测器计数率的理论计算方法，并基于运行电厂测量数据进行分析验证，为源量程探测器计数率的理论预估提供了较为完善的理论方法流程。本文结果可为无源启动源量程探测器计数率分析提供支持，同时也可用于次级中子源装载量或布置位置的优化分析等。     

Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor

Hydrogen source term and hydrogen mitigation under severe accidents is evaluated for most nuclear power plants (NPPs) after Fukushima Daiichi accident. Two units of Pressurized Heavy Water Reactor (PHWR) are under operating in China, and hydrogen risk control should be evaluated in detail for the existing design. The distinguish feature of PHWR, compared with PWR, is the horizontal reactor core surrounded by moderator in calandria vessel (CV), which may influence the hydrogen source term. Based on integral system analysis code of PHWR, the plant model including primary heat transfer system (PHTS), calandria, end shield system, reactor cavity and containment has been developed. Two severe accident sequences have been selected to study hydrogen generation characteristic and the effectiveness of hydrogen mitigation with igniters. The one is Station Blackout (SBO) which represents high-pressure core melt accident, and the other is Large Break Loss of Coolant Accident (LLOCA) at reactor outlet header (ROH) which represents low-pressure core melt accident. Results show that under severe accident sequences, core oxidation of zirconium–steam reaction will produce hydrogen with deterioration of core cooling and the water in CV and reactor cavity can inhibits hydrogen generation for a relatively long time. However, as the water dries out, creep failure happens on CV. As a result, molten core falls into cavity and molten core concrete interaction (MCCI) occurs, releasing a large mass of hydrogen. When hydrogen igniters fail, volume fraction of hydrogen in the containment is more than 15% while equivalent amount of hydrogen generate from a 100% fuel clad-coolant reaction. As a result, hydrogen risk lies in the deflagration–detonation transition area. When igniters start at the beginning of large hydrogen generation, hydrogen mixtures ignite at low concentration in the compartments and the combustion mode locates at the edge of flammable area. However, the power supply to igniters should be ensured.     

电子探针对磁铁矿中变价元素Fe的测试方法

充分利用岛津电子探针在硬件上的优势，采用全元素测试，即包括超轻元素氧在内的所有元素直接测试的思路对磁铁矿进行了测试，根据电价平衡原则计算出变价元素的含量，并使用状态分析的方法验证了FeO和Fe2O3含量的Lβ/Lα特点，得到了较为理想的测试结果。     

核电应急柴油发电机组滑油低压保护停机控制的设计优化

通过采用转速分段及增加短延时的改进方法，对当前核电应急柴油发电机组滑油低压保护停机控制设计进行了优化。经论证与试验表明:优化后的保护停机控制对机组起动及运行过程均起到了保护作用，同时确保了滑油压力的正常建立，避免了机组因受外部因素影响导致应急保护停机误动作，提高了机组起动的可靠性。该优化方案已经在核电厂应急柴油发电机组控制系统中得到广泛应用。     

非能动核电厂事故72 h后规程优化研究

事故72 h后规程是非能动核电厂特有的一类规程。为了评价非能动核电厂事故72 h后规程的必要性和充分性，并对其薄弱环节进行优化改进，本研究对示范项目非能动核电厂设计基准和运行规程体系的总体逻辑进行了分析，并基于事故72 h后规程的内容和结构，提出了评价事故72 h后规程必要性和充分性的通用方法，运用规程执行逻辑框图识别了规程执行过程中可能存在的风险项，并针对示范项目的规程提出了优化建议。分析结果表明，事故72 h后规程对于非能动核电厂的安全运行是充分必要的；其表达方式与规程体系结构相关；明确规程操作路径优先级、减少规程跳转能够提高规程执行效率。相关优化建议可为非能动核电厂事故后长期安全运行提供技术参考。