不可否认,智能技术作为驱动新一轮科技革命和产业变革的核心推手,其与制造业的深度融合将给予传统制造业充分的生命力,为制造业带来一场深刻的变革.论文在调研人工智能已有技术的基础上,以核电设计为分析对象,对智能技术在核电领域中的部分典型应用场景进行了思考,为智能化、数字化核电提供一定的借鉴.

合理有效地定量评估核安全级DCS软件的可靠性是核电数字化控制系统研制中面临的主要难题之一.文章总结了软件可靠性定量评估方法的理想特性和共同限制,调研了现有的软件可靠性定量评估方法并将其分类进行描述,最后依据10个理想特性评估现有的软件可靠性定量评估方法.研究结果可为核安全级DCS软件可靠性定量评估方法的开发提供指导,为DCS模型评估结果纳入反应堆PRA探索新的途径.

毫米波电子系统在雷达与卫星通信、电子对抗、遥测遥感、航天测控等通信接收系统领域有着广泛的应用.其中,低噪声放大器(Low Noise Amplifier,LNA)作为毫米波通信系统前端接收机的第一级关键电路,在工作带宽内将前端接收到的微弱信号进行放大,并在抑制信号噪声干扰、降低噪声系数,提高接收灵敏度起着至关重要的作用.文章研究设计了一款工作频率范围为32～38 GHz的低噪声放大器,该放大器采用赝同晶型高电子迁移率晶体管(Pseudomorphic High Electron Mobility Transistor,PHEMT)三级级联的电路结构,并采用自偏压供电.在级联的输入端通过匹配网络实现最佳噪声反射系数,在级联的输出端通过匹配电路保证高增益和最大功率传输.末级利用高通滤波器实现增益平坦性,利用电阻网络调节输出驻波比.通过仿真分析表明,该低噪声放大器在32～38 GHz工作频率范围内的噪声系数NF≤2 dB,带内增益G≥20.5 dB,输入与输出回波损耗RL≤9.5 dB.

以舰船阀门抗冲击分析要求反应谱为目标谱反演了对应的冲击时程波,基于Ansys利用瞬态动力学方法对某船用轴流式止回阀的抗冲击性能进行分析,直接在Ansys中实现了阀门在冲击载荷和连续工作载荷共同作用下应力结果的叠加.通过对应力计算结果的校核分析,证明设计的轴流式止回阀能够在要求的冲击载荷和连续工作载荷共同作用下保证结构的完整性.

文章对NaI(Tl)闪烁体探测器的探测效率使用蒙特卡罗(Monte Carlo)方法进行了模拟计算,在此过程中采用NaI(Tl)闪烁体探测器在实际使用中的封装结构.通过改变反射层的材料以及反射层的厚度(从0.1 cm到0.3 cm),得到不同反射层厚度下的仿真结果,计算出了NaI(Tl)闪烁体探测器的绝对探测效率(Absolute Detection Efficiency,ADE)以及全能峰效率(Full Energy Peak Efficiency,FEPE);根据计算得出的结果,绝对探测效率会随着反射层厚度的增加而增加,同时全能峰效率的变化趋势与绝对探测效率的变化相反.为了平衡绝对探测效率以及全能峰效率,建议选择0.1 cm厚度的反射层.

反应堆控制对象具有非线性和多变量耦合的特点,为了优化控制效果,首要任务是建立较为精确的对象模型.神经网络作为近几年较为前沿的智能算法,对非线性系统的辨识展现了明显的优越性.BP神经网络是一种多层前馈神经网络,文章基于高功率区小范围变负荷的反应堆运行数据,采用BP神经网络进行数据的训练,对训练好的网络进行测试,仿真结果验证了辨识的有效性.

文章基于对脊鳍线过渡结构设计并仿真了一种W波段的矩形波导—微带线的转换器.该转换器具有平面电路的几何结构优点,且空间体积小、质量轻,可广泛应用于毫米波平面传输线组成的电路中.通过仿真结果表明:在W波段(80～95 GHz)的频带范围内,该过渡结构的回波损耗小于20 dB,插入损耗小于0.4 dB.

采用相分析、SEM、万能拉伸试验机等手段,研究了不同时效温度对0Cr15Ni70Ti3AlNb合金组织和性能的影响.结果 表明:0Cr15Ni70Ti3AlNb合金在不同的时效温度下析出相有MC相、M23 C6相和γ'相.MC和M23 C6碳化物在650、670、690℃时的含量基本保持不变.随着时效温度的升高,γ'相的含量和尺寸不断增加.时效温度从650℃升高到720℃,γ'相质量分数由4.971％增加至10.744％,γ'相晶粒尺寸由11.0nm增大到38.8 nm.在650℃保温14h后,基体内部析出细小的球状γ'相,当时效温度为750℃时,合金内部出现链状的γ'相,当时效温度为810和840℃时,合金中存在方形的γ'相.随着时效温度的升高,合金室温抗拉强度和屈服强度呈现先增高后减小的趋势,当时效温度高于750℃后,室温抗拉强度和屈服强度均迅速下降,时效温度为720℃时,合金的冲击韧性值最小.

采用Thermo-Calc热力学计算软件,模拟计算了0Cr15Ni70Ti3AlNb合金的平衡析出相和凝固过程.结果 表明:0Cr15Ni70Ti3AlNb合金的平衡析出相主要包括γ、γ'、MC、M23C6;合金凝固过程中Ti和Nb属于正偏析,Cr、Fe、Si等属于负偏析.Al和Ti是影响0Cr15Ni70Ti3AlNb合金中γ'相析出温度和最大析出含量的主要因素.MC相的析出温度和最大析出含量主要由C元素决定.M23C6相的析出温度主要由Cr元素决定,M23C6相的析出量主要由C元素控制.0Cr15Ni70Ti3AlNb优化合金成分(质量分数)为C(0.03％～0.05％)-Al (0.7％～0.9％)-Ti(2％～2.25％)-Nb(0.75％～0.95％)-Cr(13.5％～15.5％).研究结果可为合金的成分设计和热处理工艺制定提供理论指导.

Combined with the double "O"-ring seal characteristics of the reactor pressure vessel, various affecting factors on the grinding are analyzed from the grinding mechanism, and the cross-textured grinding method of sealing surface is proposed, then the advantages of cross-textured grinding are discussed from the grinding efficiency and textured sealing features. The plan of the grinding apparatus for pressure vessel sealing surface is proposed and grinding tests are carriedout that to verify the cross-textured ground can be implemented. Practice has proved that the use of the cross-textured grinding technology can be promoted the use in pressure vessel sealing surface grinding repairs of nuclear power plants, research reactors and other devices reactor.

A new monitoring technology for control rod position is developed by utilizing the FPGA(Field-Programmable Gate Array) platform and using the SOPC(System On Programmable Chip) technology.In this SOPC system,Nios II CPU,VGA(Video Graphics Array)display controller and CAN(Controller Area Network) bus controller are integrated in one FPGA chip.Thus the SOPC hardware platform with comprehensive functionality is constructed.Based on this SOPC platform,the real time data of control rod position indication system can be vividly displayed on the LCD and stored in the external nonvolatile RAM as history records.Therefore,the operator can obtain the overall operation status of control rod position indication system quickly and conveniently.The developed prototype has proved the feasibility of this technology.

Both anti-operation probability and mal-operation probability with different structures used in shutdown reactor trip breaker are analyzed by failure-tree method.In the analysis,mal-operation probability,which is crucial for reactor safety,is especially considered to analyze the effect of shutdown operation reliability of reactor trip breaker.Results indicate that,the structure of 2/4 form reactor trip breaker for the second type is prior to other structures compared with the performance of mal-operation probability and reliability,and the improvement to decrease mal-operation probability should aim at the purpose of decreasing mal-operation probability of driving signals.