10兆瓦模块式高温气冷实验堆的设计概念及安全分析

概述了将在我国建造的10兆瓦模块式高温气冷实验堆的设计特性、安全概念及安全分析。介绍与讨论了部分设计基准事故的分析结果,包括反应性引入事故、丧失主热阱事故、主回路失压事故,以及蒸汽发生器断管事故等。初步安全分析结果表明,10兆瓦高温气冷实验堆具有良好固有安全特性,在上述假想事故工况下反应堆均处于安全允许状态。     

10 MW高温气冷实验堆事故分析的结果与对策

1 0MW高温气冷实验堆 (HTR 1 0 )的事故分析表明 ,在设计基准事故和严重事故条件下 ,HTR 1 0的堆芯燃料元件的最高温度和反应堆冷却剂系统的压力都低于规定的安全限值 ,燃料元件和冷却剂系统压力边界都能保持其完整性 ,不会造成裂变产物大量向外释放。根据事故分析结果并参照国外高温气冷堆安全运行的管理实践经验 ,针对HTR 1 0所提出的一系列事故对策有效地保证了HTR 1 0在较高的安全水平上进行设计、建造、运行及管理等 ,能够确保HTR 1 0、人员、社会以及环境的安全     

HTR-10安全负压通风系统的设计

由于高温气冷堆具有固有安全性，因此在高温气冷堆的设计中采用通风式包容体替代了密封承压式安全壳，在供暖，通风与空调（HVAC）系统中相应采用了安全负压通风系统，以保证包容体在正常工况或事故工况下都能满足与安全相关的一切功能，本文介绍了10MW高温气冷实验堆（HTR－10）安全负压通风系统的设计与评价。     

10MW高温气冷实验堆安全分析要素的定期安全审查

10 MW高温气冷实验堆(简称HTR-10)是我国第一座模块式高温气冷堆,由清华大学核能与新能源技术研究院(核研院)设计。按照我国核安全法规的要求,并经过国家核安全局的批准,核研院于2012年开始对10 MW高温气冷实验堆进行定期安全审查(简称PSR),安全分析是本次审查的重点安全要素之一。本文对安全分析要素审查的主要内容作了概述,并给出了核研院对本次审查的内部评价。     

浅析10MW高温气冷实验堆对于高温气冷堆示范工程的作用

介绍了10MW高温气冷实验堆(简称HTR-10)工程的实践经验成果,论述了HTR-10的成功对于高温气冷堆示范工程的现实意义。     

HTR-10的运行工况监督和事故工况追忆

总结了将分布式计算机控制系统（DCS）用于10MW高温气冷堆运行工况的监督和事故工况追忆的设计思路,主要包括历史数据库,事故追忆库,人机界面和运行报表的组态设计。     

HTR-10燃料元件的气体输送

为了保证高温气冷实验堆球形燃料元件可靠地输送，采用了传递管输送方法，本文介绍了10MW高温气冷堆（HTR－10）燃料元件气体输送系统的关键设备，管路设计及输送气体流量计算，通过初装料的运行，证明该系统运行良好。     

低温供热堆断电事故（ATWS）分析

文章利用RETRAN-02对清华大学在建5MW低温核供热实验堆断电事故(ATWS)进行了分析,比较了两种注硼模型,给出了事故过程描述、计算方案及计算结果。     

10MW模块式高温气冷试验堆的初步动态分析

文章针对10MW模块高温试验堆的主要设计基准事故,完成了初步的动态分析,所涉及的事故划分为四类:失压事故、失去主热阱事故、蒸发器传热管破裂和反应性引入事故。动态分析结果表明,该模块高温试验堆具有固有的事故安全性。失冷和失压工况下,由导热、辐射和自然对流等被动传热机制能将剩余发热安全地传出反应堆。当出现反应性引入或ATWS事故时,籍助负反应性温度系数,反应堆将自动停堆。在所研究的全部事故工况下,产生的燃料元件最高温度不超过970℃,远低于高温气冷堆的温度限制。     

FHR在全厂断电事故下对RVACS散热能力的要求

氟盐冷却高温堆(Fluoride salt-cooled High-temperature Reactor,FHR)是一种采用包覆颗粒燃料、高温熔融氟盐冷却剂的先进反应堆。部分FHR概念采用了反应堆容器辅助冷却系统(Reactor Vessel Auxiliary Cooling System,RVACS)导出事故下的堆芯余热。RVACS通过导热、对流换热、辐射换热等非能动过程,在事故发生时将堆芯余热排出至大气中。本文采用中国科学院上海应用物理研究所设计的10 MW FHR作为基准,利用RELAP5-MS程序,对其在全厂断电事故下的瞬态过程进行了模拟,验证了RVACS的余热导出能力。本文进一步研究了高反应堆功率情况下的全厂断电事故的瞬态过程,探讨了不同反应堆功率的FHR对RVACS散热能力的要求。     

Reactor technology development under the HTTR project

JAERI is developing HTR technology, hydrogen production technology, and system integration technology under the HTTR Project. The HTTR is the Japanese first HTR with a 30-MW thermal power. The first criticality of the HTTR was achieved in 1998, and the full-power operation at an outlet coolant temperature of 850°C was attained in 2001. The outlet coolant temperature was reached to 950°C in 2004. A seven-year program on the gas turbine HTR was launched in 2001. The program consists of the design of a GTHTR300 plant and R&D on a closed-cycle helium gas turbine system for the GTHTR300. It is designed to have a 600-MW thermal power at an outlet coolant temperature of 850°C and a 275-MW electric power. The objectives of the program are to establish a feasible plant design and to demonstrate key technologies for the helium gas turbine. The GTHTR300 design will demonstrate competitive economy and high degree of safety. It will also provide technology basis of VHTRs for power generation, hydrogen production, and cogeneration.     

HTR-10应急电力系统设计及其调试

在充分利用高温气冷堆所具有的良好固有安全性这一特点的基础上，以安全级不间断电源装置组成了静止式新型应急电源系统，从而大大地减化了系统，降低了投资，并显著地提高了系统的安全性和可靠性，本文全成介绍了10MW高温气冷实验堆（HTR－10）应急电力系统的系统功能，主要设计原则，系统组成以及应急电力系统的核心设备－安全级不间断电源装置的运行方式和安全特性，并系统地总结了应急电力系统的调试工作。     

高温气冷堆地震丧失厂外电的风险评价

地震导致丧失厂外电是核电厂地震情况下的典型始发事件。本研究使用地震概率安全分析方法,以高温气冷堆为研究对象,得到其在地震丧失厂外电事故下的风险水平。研究范围包括分析地震导致丧失厂外电的事故发展情景分析,筛选地震设备清单并结合现场巡访进行调整,建立地震导致丧失厂外电的风险评价模型,并对超过高温气冷堆风险接受准则剂量（概率安全目标）的放射性释放的频率结果进行了间隔分析、割集分析和重要度分析。本文工作可为高温气冷堆的地震概率安全分析在方法实施、建模假设、过程分析等方面提供有益的参考。     

The safety of the HTR 500

Comprehensive construction and operating experience is available in the High-Temperature Reactors constructed by the BBC group, the AVR experimental nuclear power plant and the THTR 300 MW in Hamm-Uentrop, being in its commissioning phase. The main objective pursued in the planning and design of the HTR 500 was to create a marketable and commercial plant, maintaining at the same time high safety standards corresponding to the current state-of-the-art. Thus full use is made of the system-specific safety characteristics of the HTR. In addition, the great number of probabilistic analyses likewise confirming the extremely low risk of the HTR have been used as a basis of the HTR 500 safety concept.     

浮动核电厂反应堆供电系统分析

The safety of the floating nuclear power plant is closely related to the merits of the reactor power supply system. In order to improve the safety factor of floating nuclear power plant, it is necessary to analyze the reactor power supply system. In this paper, the configuration of the reactor power supply system of the floating nuclear power plant is analyzed, and the auxiliary power system and nuclear emergency power system under two schemes are compared. The results show that the optimized scheme 2 is better than scheme 1 in reliability and safety, and scheme 2 is more economical. The optimization scheme proposed in this paper can provide a direction for the design of the reactor power supply system of the subsequent nuclear powered ships and has a strong reference significance.     

浮动核电厂反应堆供电系统分析

浮动核电厂的安全性与反应堆供电系统的优劣紧密相连，为提高浮动核电厂的安全系数，需对反应堆供电系统进行分析。本文结合反应堆供电系统设计的要点，分析浮动核电厂反应堆供电系统的配置，对比了2种方案下的辅助电力系统和核应急电力系统。结果表明，优化后的方案2在可靠性和安全性方面都较方案1更优，且方案2也更为经济。本文提出的优化方案可为后续核动力船舶反应堆供电系统的设计提供参考和借鉴。      

核电厂应急柴油发电机继电保护分析

文章主要介绍了核电厂应急柴油发电机功能与特点,在核事故情况下起到的重要性。详细介绍了继电保护的特点及保护配置,论述保护方案的合理性,能够完全满足应急柴油发电机的各种运行状态。对继电保护装置的原理、特性进行详细的论证分析,在应急柴油机出现不正常运行状态和严重故障情况下的保护动作,快速切除柴油机,防止柴油机的进一步损害;分析了应急柴油发电机在外部电源扰动情况下,继电保护装置如何快速响应,闭锁保护动作,避免应急柴油发电机不必要的情况下切除,造成应急电源失去,影响核电厂安全。同时,分析了继电保护装置保护定值的灵活应用,满足各种运行状况。阐述了核电厂由于其核安全的特殊性,导致继电保护配置的特殊性,分析了此种保护在其他设备上应用的可能性,并对设计提供的保护定值进行分析,提出自己的观点。     

Modular high temperature reactor (Modular HTR) contributing the global environment protection

Rapid increasing of the energy demand and the economic growth of the developing countries are threatening to lead to unstable supply of the fossil resources and the aggravation of the global environment. Modular High Temperature Reactor (Modular HTR) is one of the most effective solutions of such problem. The GT-MHR (Gas-Turbine Modular Helium Reactor) is a typical plant of the Modular HTR, which is a high efficiency nuclear power generating plant, combined the Modular HTR having passive safety characteristics with the direct cycle helium gas turbine. It has sufficient potential to contribute the global environment protection with keeping the growing speed of the developing countries.

Fuji Electric joined the international GT-MHR project in January 1997 and has helped to finance it. Fuji Electric, in the behalf of the other participants of this project, introduces the outline of this project and main system of the GT-MHR plant in this paper.     

High temperature reactor development in China

Since the late 1970'-s the research and development program on the high temperature gas-cooled reactor (HTR) has been carried out in China. The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) reached first criticality in 2000 and was put into full power operation in 2003. Six safety demonstration tests were done on the HTR-10. The project of the HTR-10 with a gas turbine cycle is underway. The project of the HTR demonstration plant with a power of around 150 MWe (HTR-PM) is planned. In this paper the HTR development in China is briefly described.