秦山第三核电厂为CANDU堆,其大修周期优化项目在非标定类监督要求论证时主要参照加拿大CANDU堆核电厂的论证实践,总体上从执照基准文件的符合性审查、受大修周期优化影响设备运行历史评估、系统不可用度评价和监督试验历史评价4个方面来进行定量或定性分析论证,同时还具体借鉴了美国核电厂长燃料循环论证方法中的技术规格书监督要求修改论证的实践,对每个非标定类监督要求从6个方面进行论证总结.

现有的CANDU重水堆(简称“重水堆”)以天然铀作为燃料,但重水堆由于其独特的堆芯设计,具有较好的燃料灵活性,还可以烧低浓铀、回收铀和钍等燃料.研究现有重水堆改烧钍燃料后对堆芯特性和运行安全的潜在影响.使用DRAGON程序建立了重水堆的无限栅元模型,研究比较了钍燃料和天然铀燃料的重要堆芯特性参数.结果表明,尽管2种燃料下的堆芯特性有所差异,但钍燃料利用实际上有助于提升重水堆的运行安全.

Recycled uranium (RU), as a sort of nuclear resources, becomes more and more important along with the global development of nuclear power and the rising of natural uranium price, but it is difficult to use RU currently. Since there are both PWRs and CANDU reactors in China, a plan was brought forward to use RU reprocessed from PWR spent fuels in CANDU reactor in a form of NUE type firstly, which is combination of RU and depleted uranium (DU) and is neutronically equivalent to natural uranium. For this fuel, the demonstration test was conducted in Qinshan CANDU unit 1, to obtain the experiences of RU manufacturing and operating and to provide technical support to NUE fuel full core implementation in Qinshan CANDU units.

The neutronics behavior of the test reactor core fuelled with natural uranium equivalent(NUE) was analyzed based on the neutronics design code system for CANDU reactor.The NUE two-channel test reactor core was demonstrated,and the analysis results were compared with the safety criteria and neutronics behavior of the corresponding fully natural uranium(NU) filled core to confirm the neutronics equivalence of NUE fuel.The study shows that NUE fuel filled in testing reactor meets the neutronics equivalence requirement.The test irradiation of NUE fuel in two channels of a CANDU reactor core with NU fuel is feasible in the neutronics design,and the introducing NUE has no impact on the core safety assessment.

A risk monitor,an integrated risk analysis tool for real-time monitoring,was widely used in the management of nuclear power plants around the world.A risk monitor prototype system,named RiskAngel,has been developed by FDS Team,China,in which the fault tree analysis engine RiskA was integrated.Based on these,Third Qinshan nuclear power plant Risk Monitor(TQRM) has been developed considering the safety characteristics and the management process of Third Qinshan nuclear power plant.The status and development trend of risk monitor were given in this paper.An overview of the architecture and functions of TQRM was introduced.The key algorithms and technical features were also presented.

与作为技术主流的压水堆相比,重水堆因其独特的堆芯设计和运行特点,具有燃料灵活多样、铀资源利用率高、可利用钍资源和回收铀、可大量生产60Co等多种同位素的技术优势。秦山三核正在根据重水堆的比较优势开发重水堆相关技术,目前已经实现60Co生产棒束入堆,并正在联合国内外科研院所研发重水堆回收铀应用和重水堆利用钍资源技术。一旦实现重水堆利用回收铀或重水堆利用钍技术,重水堆运行将不再大量消耗天然铀资源,对后续在其他堆型推广应用,多渠道解决核燃料供应并促进核电产业的科学发展均意义重大。

Physical startup and physical commissioning test of CANDU 6 during commissioning are primarily performed at Phases B and C, and critical monitoring after fuel loading at PHASE A is also included. Based on physical commissioning of Wolsong Unit 4 of Korea, the pre-modeling analysis, test method as well as analysis evaluation of the test results of the physical commissioning test data, indicating the points for attention during testing are presented.