共查询到19条相似文献,搜索用时 140 毫秒
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多用途放射性废物焚烧系统工程验证试验 总被引:7,自引:4,他引:3
对建立的多用途放射性废物焚烧系统,进行了工程验证试验。试验主要包括固体废物(包括树脂)和废油焚烧及烟气净化时系统的性能测定、非放示踪试验、72h连续运行考验等。经过共计500多小时的试验,验证了工艺流程、主要设备结构、仪表测控及系统安全等设计的可行性和可靠性;系统运行平稳,设备及仪表工作正常。本系统可一炉多用,其处理能力、减容系数、焚烧灰中残炭率以及系统总去污系数等指标,均达到了设计要求。 相似文献
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介绍了用于核电站控制区进出口辐射监测闸门的单片机测控系统的软硬件设计,主要功能及特殊功能,硬件故障的自诊断、等。 相似文献
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控制棒水力驱动系统的设计和研究 总被引:23,自引:2,他引:21
分析了200MW核供热堆控制棒水力驱动系统的设计特点;系统中主要设备的设计特点及特性;旁路自调节结构的设计及其高温下的补偿作用以及系统温度特性的实验结果。经对实验结果的分析表明:HDSCR和各设备的设计合理,运行可靠;各设备的设计不仅降低了设备的加工难度及安装难度,而且改善了系统的温度特性;系统安全能满足200MW核供热堆对控制棒驱动机构的要求。 相似文献
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随着放射性可燃固体废物焚烧站的生产运行,焚烧系统的设备及工艺管路不可避免地出现了不同程度的腐蚀,如果该系统中的关键设备及管路出现了严重的腐蚀问题,将会影响整个系统的安全平稳正常运行。文章阐述了系统经过生产运行后各个关键设备及管路的腐蚀现状,从工艺设计和生产运行角度分析了设备的腐蚀原因,针对由电偶腐蚀、点腐蚀、缝隙腐蚀等不同腐蚀机理造成的腐蚀进行了探讨;同时,文章还从放射性废物管理及工艺控制角度,提出了减缓系统设备腐蚀的建议。 相似文献
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Instantaneous radiation, mainly consisting of photon and neutron caused by beam loss, occurs during the debugging and operation of the 100 MeV cyclotron. Some components such as beam line, targets and collimators will generate residual radiation while they are impinged by the beam. And worse still, sometimes this may lead to the destruction of relevant devices. In order to avoid the radiation damage to the device as well as people involved, it is planned to implement a set of radiation monitoring and safety system, aiming to protect devices and ensure personnel safety by monitoring the parameters of the beam and dose rate of different areas. 相似文献
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核电站蒸汽发生器降质预防和在役检查 总被引:2,自引:0,他引:2
丁训慎!核动力运行研究所 《核科学与工程》1999,(3)
介绍了法国核电站蒸汽发生器在运行初期所发生的传热管降质现象,重点论述了大亚湾核电站1 号机组蒸汽发生器对降质预防所采取的措施和在役检查,包括二回路水化学监控、泄漏率监测、传热管涡流检验、二次侧的机械清洗、清洁度检查和外来物取出等。实践证明,采取了上述降质预防措施和在役检查,对核电站的安全运行起到了重要作用 相似文献
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针对基于计算机技术的数字化仪控系统可能存在软件共因故障问题,设计了一个安全系统系统级手动驱动系统。该系统用以在计算机技术实现的保护系统失效后执行安全功能。本文介绍了与该系统相关的安全系统的系统级操作、事件级的电站状态监视、定期试验、非计算机化设备、独立性、多样化等内容。这些特点能够保证在采用计算机技术的反应堆保护系统失效后,提供有效的安全功能执行手段,缓解事故后果。该系统弥补了计算机化仪控系统的弱点,能够防止软件共因故障。 相似文献
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E.O. Adamov I.I. Grozdov S.P. Kuznetsov A.A. Petrov M.I. Rozhdestvensky Yu.M. Cherkashov 《Nuclear Engineering and Design》1994,147(1)
Following the search for new design solutions to develop within the framework of channel trends the reactor with enhanced safety the Research and Development Institute of Power Engineering has developed the design of the multiloop boiling water reactor (MKER). The MKER enhanced safety is attained when involving the inherent safety features, passive safety systems as well as the accident consequences confinement devices. The design realizes several advantages which are typical of the channel-type reactors, namely: the design desintegration simplifying the manufacture, control, equipment delivery and decreasing, versus the pressure vessel reactors, the accident effect if it proceeds in an explosive manner; small operating reactivity margin and fuel burnup increased due to continuous refuelling; fuel cycle flexibility allowing comparatively easily to adopt the reactor to the conjuncture of the country fuel balance; multiloop circuit of the main coolant which reduces the degree and effect of the accidents connected with the equipment and pipings rupture; monitoring of the channels and fuel assemblies leak-tightness. 相似文献
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辐射防护监测系统是中国先进研究堆(CARR)的一个重要辅助系统,对系统中燃料破损辐射监测、主控室可居留性辐射监测和烟囱排风辐射监测三方面进行了设计优化。设计优化后的结果是在满足系统功能,把握"安全可靠,经济适用"的原则下,使优化后设计更加符合CARR运行的实际需要。 相似文献
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Operating experience of pressurised components is reported on the basis of 19 light-water reactors operating in Germany. The design basis and materials have demonstrated their worth. Licenses are not limited in time, and the major regulatory effort is directed to continuous improvement in plant safety. Technical issues for long-term operation as evaluation of operating experience, plant monitoring, replacement of components are addressed. The basic safety concept as the design basis for the pressurised components is illustrated by some of its details. The main results from the analysis of operating experience are mentioned. Plant monitoring and inspections are important measures to ensure the integrity of the components and to maintain the safety level of the plant. The expansion of the monitoring system may allow a reduction in the scope of inspections. 相似文献
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目前国内核电厂主要采取定期校准的方式对安全级仪表漂移进行管理,但该方法过于保守且经济性差。基于此,本文对安全级仪表在线监测系统技术进行了研究,首先对安全级仪表实际漂移数据进行了分析,明确了核电厂安全级仪表漂移的主要类型,证明了对安全级仪表开展在线监测的可行性。其次,通过对相关法规及标准的分析和研究,明确了核电厂安全级仪表在线监测技术的基本要求。最后,开展了在线监测系统技术的数据分析研究,对冗余仪表提出了等价平均算法,对非冗余仪表算法进行了分析并对多元状态估计模型(MSET)方法开展了基于电厂实际数据的建模验证,证明了该方法在核电厂应用的可行性。 相似文献