核动力领域元器件辐射效应及抗辐射加固需求分析研究OA
Analysis of Radiation Effects and Radiation Hardening Requirements for Components in the Nuclear Power Field
随着核反应堆逐渐向轻量化、小型化的方向发展,反应堆屏蔽重量不断降低,仪控系统所在区域的辐射剂量将提高,部分传感器类仪控设备甚至需要工作在强辐射环境中.为应对未来核反应堆环境对仪控系统元器件抗辐射性能的严峻挑战,本文开展了核动力领域元器件辐射效应及抗辐射加固需求分析研究.首先,开展了核电厂等核设施辐射环境条件分析研究;其次,分析了元器件的常见辐射效应,并结合核反应堆环境特点对元器件失效进行了分析;最后,针对仪控系统中核探测器类设备、压力变送器类设备、核环境作业机器人类设备等进行了需求分析论证.需求分析结果表明,目前阶段核动力领域仪控系统中,部分设备需要开展辐射效应研究并且制定有效的抗辐射加固措施,才能有效提高核动力领域核反应堆环境下仪控系统的抗辐射性能.
With the development of nuclear reactor technology,reactors are gradually moving toward lightweight and miniaturized designs.With the reduction of reactor shielding,the radiation dose rate of the instrumentation and control(I&C)system increases significantly,and some sensor-based I&C system will work in high radiation environment.To address the severe challenges posed by future nuclear reactor environments to the radiation resistance of the instrumentation and control system,a study on the analysis of radiation effects and radiation hardening requirements for components in the nuclear power field is conducted in this paper.Firstly,the analysis of the radiation environment in nuclear power plants and related facilities is conducted.Subsequently,common radiation effects of components are analyzed,and their failures are evaluated in conjunction with the specific characteristics of the reactor environment.Finally,the requirements analysis and demonstration are performed for key instrumentation and control systems,including nuclear detectors,pressure transmitters,and robotics.The results show that,at the current stage,studies of the radiation effects and effective hardening measures must be considered for certain instrumentation and control systems in the nuclear power field to ensure enhanced radiation resistance.
杨振雷;何正熙;陈美远
中国核动力研究设计院先进核能技术全国重点实验室,成都 610213中国核动力研究设计院先进核能技术全国重点实验室,成都 610213中国核动力研究设计院先进核能技术全国重点实验室,成都 610213
信息技术与安全科学
核反应堆仪控系统元器件抗辐射加固需求分析
nuclear reactorinstrumentation and control systemcomponentsradiation hardeningrequirements analysis
《现代应用物理》 2026 (3)
129-136,8
中国核动力研究设计院原创基金资助项目(Z403202301002)先进核能技术全国重点实验室基金资助项目(YNSW-0124-0304-23)
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