共查询到18条相似文献,搜索用时 125 毫秒
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本文介绍了模块化高温气冷堆的安全特点,对反应堆堆芯设计核安全审评重点关注的核安全问题进行了分析,并提出解决方案以供设计和审评人员参考。 相似文献
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本文介绍了模块化高温气冷堆的安全特点,对反应堆堆芯设计核安全审评重点关注的核安全问题进行了分析,并提出解决方案以供设计和审评人员参考。 相似文献
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美国核学会访华代表团成员理查德(C.L.Richard)于1980年9月29日在北京作了题为《多用途高温气冷堆》的报告,摘要如下:高温气冷堆 HTGR 是唯一的一种能同时发电和提供工业用热的多用途核反应堆。一座85万千瓦(热)的高温气冷堆热源代替化石燃料,一天可以节省石油11,500桶或3,000吨煤(热当量)。美国研究的发电用高温气冷堆,有蒸汽循环高温气冷堆(HTGR-SC)[功率从84—336万千瓦(热)]和氦气轮机高温气冷堆(H-TGR-GT)(功率为200万千瓦(热)]两种。美国研究的发电和供热两用高温气冷堆有三种:第一种是利用圣符仑堡堆已有技术 相似文献
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分析了发展高温气冷堆核电站的必要性,介绍了高温气冷堆发电技术的特点、现状和我国高温气冷堆核电站示范工程的建设情况,提出了充分发挥高温气冷堆发电技术特点、进一步开发高温气冷堆核电站的设想,认为条件成熟情况下,高温气冷堆核电站将有很大的商业推广价值。 相似文献
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[《日本原子》1986年6月号第15页报道]日本原子力产业会议向日本原子能委员会高温气冷堆(HTGR)研究与发展计划咨询委员会递交了一份关于发展多用途高温气冷堆的报告。目前,日本原子能委员会正在讨论如何发展高温气冷堆,并将其引入非 相似文献
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高温气冷堆是我国具有完全自主知识产权的第四代先进核能技术,具有固有安全性、模块化设计及建造、发电效率高、用途广泛等特点。文章介绍了高温气冷堆产业化推广以及高温气冷堆在替代中小火电、制氢、石化和海水淡化等领域多功能综合利用的发展前景,分析了高温气冷堆产业化面临的挑战,指明了高温气冷堆产业化发展的重要意义。 相似文献
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《核技术(英文版)》2015,(5)
Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done. 相似文献
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高温气冷堆核电厂采取多个反应堆模块匹配1个汽轮机的设计方式,即1台高温气冷堆机组会包含多个反应堆模块,这使多个高温气冷堆模块在地震外部事件下存在明显的相关性,因此在利用概率风险分析方法来全面地识别和评价高温气冷堆的地震风险时,需要从机组的角度充分考虑和模化机组内多个反应堆模块间的相关性。高温气冷堆示范电站已完成了较为完整的单模块地震概率安全分析,本文将以该分析结果为基础梳理出高温气冷堆多模块地震概率安全分析的关键技术要素并进行研究,研究内容包括多模块事件序列建模和地震相关性失效评价等关键技术,并针对多模块高温气冷堆提出了应用策略。然后以双模块设计的高温气冷堆示范电站为对象,以地震导致丧失厂外电始发事件为代表,对多模块高温气冷堆地震概率安全分析进行了实例分析获得远低于概率安全目标的释放类频率,且分析得到了高温气冷堆多模块事件序列建模策略与地震相关性失效的评价路线可行这一重要结论。 相似文献
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The modular high-temperature gas-cooled reactor (MHTGR) has distinct advantages in terms of inherent safety, economics potential, high efficiency, potential usage for hydrogen production, etc. The Chinese design of the MHTGR, named as high-temperature gas-cooled reactor-pebble bed module (HTR-PM), based on the technology and experience of the HTR-10, is currently in the conceptual phase. The HTR-PM demonstration plant is planned to be finished by 2012. The main philosophy of the HTR-PM project can be pinned down as: (1) safety, (2) standardization, (3) economy, and (4) proven technology. The work in the categories of marketing, organization, project and technology is done in predefined order. The biggest challenge for the HTR-PM is to ensure its economical viability while maintaining its inherent safety. A design of a 450 MWth annular pebble bed core connected with steam turbine is aimed for and presented in this paper. 相似文献
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Tritium behavior in the reactor such as production, diffusion and release are accompanied by their adsorption and desorption in graphite materials, which are essential to the safety of high temperature gas cooled reactor (HTGR). In order to study this important issue, hydrogen instead of tritium is experimentally used in this work and justified viable by theory. By performing multiple sets of comparative experiments, the features of hydrogen adsorption and desorption behavior changing by adsorption temperature and time in typical graphites used in HTR-PM (High Temperature Gas Cooled Reactor – Pebble Bed Module), i.e. reflective layer, fuel element and boron carbon bricks, have been observed and analyzed. Furthermore, the adsorption rates of hydrogen in the three materials as above at different conditions are also given. Based on the experimental results, tritium behavior in the HTR-PM was inferred and estimated, which is significant for the further study on the mechanism of tritium transport. 相似文献
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Ding She ing Xia Jiong Guo Chun-Lin Wei Jian Zhang Fu Li Lei Shi Zuo-Yi Zhang 《核技术(英文版)》2021,32(9):9-15
The high-temperature reactor pebble-bed mod-ule (HTR-PM) is a modular high-temperature gas-cooled reactor demonstration power plant. Its first criticality exper... 相似文献
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进气事故是模块式高温气冷堆(HTR-PM)事故分析中重点考虑的一种事故类型。核级石墨在高温气冷堆中被广泛用作反射层材料、结构材料和慢化材料等。在进气事故中,燃料元件基体石墨发生氧化反应增加了燃料颗粒裸露和放射性释放的风险,底反射层发生氧化反应降低了石墨材料的机械性能,可能破坏堆芯底部结构的完整性。本文利用高温气冷堆专用系统分析程序TINTE,分别选取两种不同氧化速率的石墨材料作为底反射层材料,以热气导管双端断裂的进气事故为例,分析不同材料对进气事故的影响。在保证底反射层完整性的前提下,底反射层采用高氧化速率的材料时,能明显降低燃料颗粒裸露和放射性释放的风险。 相似文献
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运用机械可靠性理论,利用力学仿真分析高温气冷堆示范工程——球床模块式高温气冷堆核电站(HTR-PM)控制棒组件的受力情况和薄弱区,识别出其薄弱区位于控制棒组件连接头位置;基于概率断裂力学的可靠度-寿命计算方法,结合辐照对疲劳寿命模型的影响,并考虑所受应力情况,建立可靠度-寿命模型,计算HTR-PM控制棒组件在辐照减弱系数为0.7时的可靠度-寿命。计算结果表明,可靠度水平为0.99时,HTR-PM控制棒组件寿命约为15万次动作循环,辐照对控制棒组件寿命影响较大。本研究可为HTR-PM控制棒组件设备可靠性管理提供参考。 相似文献