安全注入系统与安全壳喷淋系统早期互为备用事故策略研究

在大部分CPR1000堆型核电厂中,安全注入系统（RIS）和安全壳喷淋系统（EAS）的互为备用仅应用于大LOCA(Lossofcoolantaccident)事故工况后15天。阳江核电厂5号、6号机组进行了H4管线（安全注入系统和安全壳喷淋系统互为备用的连接管线）改进,将安全注入系统和安全壳喷淋系统的互为备用也可应用于中、小LOCA事故的早期工况。本文研究RIS系统和EAS系统早期互为备用在状态导向法事故运行程序SOP(StateOrientedProcedure)中的应用,结合基于H4管线改进的现实性事故分析,设计出中、小LOCA叠加H4工况（低压安注泵全部失去或喷淋泵全部失去）事故处理的策略及手段。     

CPR1000核岛ECCS设计优化

在CPR1000堆型现有设计方案中,安注管线上没有热交换器,发生LOCA等事故后,需要安注系统和安全壳喷淋系统同时运行才能将堆芯热量导出安全壳。本文基于"CPR1000核岛ECCS(应急堆芯冷却系统)设计综合优化"的理念,提出对CPR1000现有H4管线进行改进,克服现有H4管线只能用于远期互备的缺点,实现事故后安注系统和安全壳喷淋系统快速互备的目的,提高CPR1000核电站的安全性。此外,通过本改进的实施,可以在事故稳定后适时停止安全壳喷淋,从而终止事故后对安全壳地坑滤网危害性较大的化合物的产生过程,提高事故后ECCS的长期安全性。     

联轴器螺栓断裂原因分析与改进

从化学成分、断口形貌等方面对联轴器螺栓断裂原因进行分析,问题批次螺栓失效形式属于氢脆断裂,是螺栓强度高、硬度高、钢中存在残留的氢等因素综合作用的结果。通过改进螺栓型式、表面处理工艺优化、降低螺栓抗拉强度等措施控制螺栓质量。改进后的双头螺柱满足低压安全注入系统(RIS)安注泵、安全壳喷淋系统(EAS)安全壳喷淋泵的安全运行要求。     

压水堆核电厂事故工况下最大上充流量的数值研究

使用计算流体软件Flowmaster 7.5模拟了某压水堆核电站的化学和容积控制系统(RCV)以及安全注入系统(RIS)。通过将正常工况下的模拟计算结果与设计参考值进行对比,验证了模型的可靠性。使用该模型预测了发生蒸汽发生器传热管破裂事故(SGTR)后安全注入模式转为上充模式时最大上充流量与一回路压力的关系,并定量比较了采用不同数量的低压安注泵为上充泵增压时最大上充流量和相应主泵密封注入流量与一回路压力的关系。     

AP1000核电厂IRWST低压安注性能研究

本文采用AFT Fathom软件分析了AP1000核电厂安全壳内置换料水箱(IRWST)的低压安注性能,分析了AP1000核电厂在压力容器直接注入管线双端断裂工况下事故后期的安全注射能力。分析结果表明,AP1000核电厂低压安注能力足以带出堆芯热量,并有较大的裕量。     

核电厂安全壳地坑滤网堵塞问题研究进展与现状

安全壳地坑是压水堆核电厂专设安全设施安全壳喷淋系统和安全注入系统的重要组成部分。失水事故后安全壳地坑滤网的堵塞将极大地影响安全壳喷淋系统和安注系统的正常运行,威胁核电厂的安全。许多核电国家针对地坑滤网堵塞问题进行了研究,各国核安全管理当局也发布了公告要求核电厂解决此问题。本文介绍了安全壳地坑滤网堵塞问题的研究进展及现状。     

基于MAAP5程序的秦山核电站严重事故分析

应用MAAP5程序建立了秦山核电站一、二回路,安全系统以及安全壳的模型,并以冷段双端断裂叠加高高、高、低压安注失效,安全壳喷淋系统失效为例,对该严重事故序列进行了模拟计算,给出了瞬态过程一些重要参数随时间的变化规律。结果表明：在72 h内无能动干预手段的条件下,安全壳的完整性可得到保证,相关数据可为秦山核电站严重事故预防和事故缓解措施的制定提供重要参考。     

2×600MW核电厂超基准事故及其处理规程研究

本文对秦山二期核电厂可能发生的起基准事故进行了初步讨论．其中对全部丧失热阱、全部丧失给水和全部丧失电源等事件，以及低压变注泵和安全壳喷淋泵功能丧失事件进行了具体的分析．并对处理这些特殊事件的规程进行了讨论．     

中压安注对RRA连接模式下严重事故进程影响分析

针对中国改进型百万千瓦级压水堆（CPR1000）核电机组在中间停堆反应堆余热排出系统（RRA）连接模式下失去高低压安注和喷淋的冷却剂丧失事故（LOCA）,采用MAAP5程序对参考机组的反应堆堆芯、反应堆冷却剂系统以及安全壳系统进行模拟计算,同时结合计算结果分析中压安注系统对该严重事故序列进程的影响,并研究其对事故的缓解作用。分析结果表明,在RRA连接模式下出现LOCA导致的堆芯裸露和升温过程中,中压安注的及时注入能有效地限制堆芯的升温行为,并可对严重事故进程起到重要的缓解作用,甚至为事故工况下失去高低压安注和喷淋时避免堆芯完整性遭到破坏提供可能。最后,根据分析结果针对现行核电机组的运行规程提出改进建议:对于中压安注箱的行政隔离行为,只对其电气开关做相应的隔离操作,而对安全壳厂房内的阀门就地部分做挂牌警示,不做现场挂锁的操作,这样不仅可避免在正常运行工况下中压安注箱误注入行为的发生,同时能够在RRA连接模式下发生LOCA时有效地保障堆芯的完整性,在保证电厂正常安全运行的同时,提高了机组在该模式下发生严重事故的缓解能力。      

核电厂安全壳地坑滤网堵塞问题的机理分析

破口失水事故工况下,大量碎片可能随着泄漏的冷却剂和喷淋液迁移到安全壳地坑滤网处,并逐渐堆积形成碎片床,不断增大流体通过滤网的阻力,降低应急堆芯冷却系统或安全壳喷淋系统泵的净正吸入压头裕量并导致堆芯、安全壳丧失冷却,从而威胁核电厂安全。本文对核电厂发生假想破口失水事故后碎片的产生、迁移,以及在安全壳地坑滤网处堆积成碎片床,并造成地坑滤网堵塞的机理进行分析说明。     

医源性电离辐射损伤及其生物医学防护

随着核与辐射技术在医学检查、诊断和治疗领域运用的增加,世界范围受照人群不断增多,医源性辐射已成为人类最主要的人工辐射来源之一。医疗机构和个人在选择利用放射手段获取诊断和治疗利益的同时,需要注意和防护伴随的辐射损伤效应。本文介绍了医源性辐射及其危害、机体组织的辐射损伤特性和类型、辐射生物效应分子及效应调节研究的进展,简要概述目前临床已经使用或最具应用潜力的辐射防护策略。     

Sorption methods of separating barium and radium,aluminum and gallum,and zirconium and hafnium

Chromatographic methods of separating elements with very similar properties have now been developed. However, a number of these methods are difficult to use industrially as their throughput is low. The efficiency of chromatographic separation methods could be increased considerably by using appropriate complex formers, which decrease the effective concentration of the ions being separated, and,in the first approximation, this is equivalent to a decrease in the amount of elements being separated. The difference in the formation constants of the complex compounds increases the separation coefficient. By investigating chromatographic separation with the use of various complex formers, we found the optimal conditions for separating barium and radium, zirconium and hafnium, and aluminum and gallium. The throughput of these methods, with respect to the macroelement was 15–60 kg/hr per m² of column cross section.     

Distribution and Fixation of Cesium and Strontium in Zeolite A and Chabazite

The selective removal and fixation of Cs and Sr have been studied in zeolite A and chabazite. Cesium ion was preferentially distributed into chabazite with a high distribution coefficient (K _Cs>10³ cm³·g^?1) in the presence of NaCl (10^?1 mol·dm^?3). The K _Sr values for zeolite A attained about 10³ cm³·g^?1 in the pH range of 8～10, and they gradually decreased with an decrease in pH.

The initial rate of Cs adsorption was fairly fast in chabazite, and the adsorption ratio reached almost 100% within a few hours. The adsorption ratio of Sr in binderless A zeolite reached almost 100% after 15 h. The adsorption of Cs and Sr on these zeolites was followed by Langmuir-type isotherm. Cesium forms of these zeolites recrystallized to pollucite (CsAlSi₂O₆) above 900°C for zeolite A and above 1,200°C for chabazite. As for Sr forms, these zeolites changed to SrAl₂Si₂O₆ above 900°C.

These recrystallized phases were suitable hosts for the immobilization of Cs and Sr in the nuclear waste solutions.     

清洁解控和退役若干动向与新发展

对国际辐射防护协会第 1 0届大会 ( IRPA-1 0 )涉及的清洁解控和退役问题作了论述 ,包括排除、豁免、清洁解控和废物最少化 ;退役工程技术的发展 ,包括去污技术、切割解体技术、探测技术 ;介绍了一个研究堆退役例子和加速器退役 ;最后 ,还论及了退役中受关注的一些问题 ,如 :石墨废物、混凝土废物、重水堆退役的氚防护、退役时间和退役废物量等。     

Plastic and dissipated work and stored energy

This paper depicts one theoretical and experimental method to take into account the energy phenomena, associated with the elasto—plastic deformation process, during the elaboration of behaviour laws. The energy balance definition is examined in order to relate the stored energy of cold work to the hardening state variables. Two experimental approaches are used to study the evolution of the energy balance. The first one uses microcalorimetric technique and the second infrared technique. Several industrial metallic materials are studied by both approaches. Energy data are used to control the validity domain of the classical behaviour laws and to elaborate new more appropriate ones. Therefore, the hardening parameters cannot be identified with the thermodynamical forces. The use of energy considerations allows the definition of new thermodynamical forces and state variables, in the case of isotropic or kinematical hardening.     

Development and diversity and defense-in-depth application of ABWR feedwater pump and controller model

This work developed an advanced boiling water reactor (ABWR) feedwater pump and controller model, which was incorporated into Personal Computer Transient Analyzer (PCTran)-ABWR, a nuclear power plant simulation code. The feedwater pump model includes three turbine-driven feedwater pumps and one motor-driven feedwater pump. The feedwater controller includes a one-element/three-element water level controller and a specific feedwater speed controller for each feedwater pump. The performance tests, including step change of dome pressure, feedwater pumps transfer, inadvertent closure of all turbine control valves, and one feedwater pump trip at 100% power, demonstrate the feasibility of dynamic response of stand-alone model and incorporated model. Furthermore, a diversity and defense-in-depth analysis is performed to demonstrate the feasibility for motor-driven feedwater pump as an emergency core cooling system (ECCS) automatic diverse back-up. In Lungmen nuclear power plant (NPP), a diverse manual initiation means for the high pressure core flooder (HPCF) loop C is designed as the back-up of digitalized engineered safety features actuation system (ESFAS). If the motor-driven feedwater pump (MDFWP) can be an automatic digital diverse back-up for ESFAS, Lungmen NPP would be more robust to defend against software common-cause failure (CCF).     

Construction and operational experience with small and medium power reactors and expected improvements

Past experience with small and medium power reactors (SMPRs) in the areas of construction and operation is examined in this paper. Current development of SMPRs focuses on passive safety features; larger design and safety margins; reduction of construction periods through simplification, modularization and increased shop fabrication.     

全国核与辐射安全监管信息系统的研究和建议

文章简要介绍了全国核与辐射安全监管信息系统的前期规划建设情况,包括基本建设内容、系统总体架构、以及工作中发现的影响和制约工作开展的主要问题,并提出了建议。