Y型截止阀在液态铅铋中流阻测量与分析

液态铅铋合金是加速器驱动次临界系统(Accelerator Driven Sub-critical System,ADS)反应堆主选冷却剂材料之一,阀门是高温液态铅铋实验回路的重要组成部件之一,它的流动阻力大小直接影响整个回路装置的结构设计与安全运行。基于液态铅铋流体测量技术实验回路PREKY,开展了Y型截止阀在液态铅铋堆典型工况下的阻力特性测量实验研究,利用压差变送器获得压差实验数据,并与理论计算结果进行对比分析,验证了实验测量方法的可行性和测量结果的合理性。另外,获得了流速1.2–2.0 m·s-1内液态铅铋介质中Y型截止阀流阻理论计算指数x值为2.4,此值可直接应用于未来液态铅铋实验回路流阻计算与分析工作。     

液态铅铋氧浓度测量技术初步研究

液态铅铋合金是加速器驱动次临界系统(ADS)中散裂靶兼冷却剂的主要候选材料。氧浓度是影响液态铅铋合金(LBE)对结构材料腐蚀的关键因素,而氧传感器是实现液态铅铋合金中氧浓度精确测量的重要部件,本研究设计研制了一种液态铅铋系统氧传感器并基于自主研制的高温液态铅铋合金氧测控预研平台,初步开展了氧饱和LBE中的氧浓度测量实验。实验结果显示,300～400℃的氧饱和LBE中,氧传感器的电压信号(E)随温度(T)变化的实验曲线与理论曲线变化趋势相吻合;相对于300℃T350℃温度范围,氧传感器在350℃T400℃范围内的测量性能更好,仪器本身的系统误差约为17mV。     

Preliminary study on the measurement technology of oxygen concentration in liquid lead bismuth

液态铅铋合金是加速器驱动次临界系统(ADS)中散裂靶兼冷却剂的主要候选材料.氧浓度是影响液态铅铋合金(LBE)对结构材料腐蚀的关键因素,而氧传感器是实现液态铅铋合金中氧浓度精确测量的重要部件,本研究设计研制了一种液态铅铋系统氧传感器并基于自主研制的高温液态铅铋合金氧测控预研平台,初步开展了氧饱和LBE中的氧浓度测量实验.实验结果显示,300～400℃的氧饱和LBE中,氧传感器的电压信号(E)随温度(T)变化的实验曲线与理论曲线变化趋势相吻合;相对于300℃＜T＜350℃温度范围,氧传感器在350℃＜ T＜400℃范围内的测量性能更好,仪器本身的系统误差约为17mV.     

液态铅铋回路设计研制与材料腐蚀实验初步研究

铅铋合金共晶体是加速器驱动次临界系统(ADS)重要的散裂靶材料和冷却剂候选材料,也是先进快中子堆的重要冷却剂材料,液态铅铋回路是开展液态铅铋合金相关技术研究的必备实验平台。FDS团队正在设计研制KYLIN系列铅铋实验回路,本文基于中国首座热对流铅铋回路KYLIN-Ⅰ开展了马氏体钢T92、CLAM和奥氏体钢316L在480℃下,流速为0.14 m/s的饱和氧浓度铅铋中的腐蚀实验研究。初步实验结果显示,三种实验材料均发生氧化腐蚀。     

液态铅铋合金流动速度场测量技术研究

液态铅铋合金是先进反应堆-加速器驱动的次临界系统(ADS)优选的靶材和冷却剂材料,液态铅铋流动速度场的测量是优化堆芯组件分布以及靶窗结构的一种重要手段。同时,冷却剂流动速度也是反映反应堆热工水力特征的重要参数之一。本文采用实验研究的方法,设计旋转搅动装置,通过对常温水与液态铅铋的流动速度场测量,验证了超声多普勒测速技术用于液态铅铋合金速度场测量的可行性。     

静态铅铋中Pt/Air型氧传感器性能初步研究

液态铅铋合金氧测控作为加速器驱动次临界系统(ADS)的关键技术之一,对抑制结构材料腐蚀具有重要作用。为深入开展氧测控技术研究,自主研制液态铅铋氧测量及控制实验装置,并基于该装置开展Pt/Air型氧传感器在饱和氧浓度下的稳定性与精确性测试实验。结果显示,在625~786K温度范围内,Pt/Air型氧传感器电压信号经过传热产生的弛豫(750s)之后稳定性表现良好,测量值的最大绝对偏差为10mV,最大相对偏差为1.5%,与理论值符合较好,其偏差主要来自热电压及氧化物的影响。     

铅铋循环回路小破口事故计算模型研究

铅铋循环回路小破口事故对加速器驱动次临界洁净核能系统(ADS)的安全有重要影响。通过建立一个铅铋循环回路小事故模型,计算分析未破口和小破口以后的铅铋循环回路参数。计算表明:小破口事故相比未破口回路压力下降梯度变大,流量迅速丧失;破口瞬态流量陡降至与进口平衡;破口与管壁压力都会随时间下降直到平衡。     

叶顶间隙结构对轴流铅铋泵叶轮磨损特性的影响

铅冷快堆反应回路中的高温液态铅铋金属会对轴流铅铋泵叶轮叶片头部产生冲刷磨损效应,造成叶片表面保护层破裂从而加快材料腐蚀速率。为了降低高温液态金属对叶片表面的冲刷磨损效应,设计平面、倒直角和倒圆角的三种叶顶间隙结构,并通过缩比换算方法验证仿真结果的可靠性,继而采用ANSYS CFX流体动力学软件分析了不同叶顶间隙结构下的流速、剪切力、流态随冲刷磨损特性变化规律,并利用壁面熵产率方法分析了高温液态铅铋金属在材料表面的能量损耗。结果表明：标准工况下倒直角模型的扬程和效率较平面分别降低了1.02%和0.64%,倒圆角模型扬程降低了0.51%,而效率提升了0.51%。叶轮内冲刷磨损效应主要发生在叶片轮缘进口边附近,倒直角和倒圆角设计可以通过降低叶顶间隙的流速和改善流态的途径减小叶片表面机械能损耗,从而降低该位置的冲刷磨损效应。因此倒圆角设计和倒直角设计能够改善高温液态铅铋金属对叶片头部冲刷磨损的影响。     

中国加速器驱动嬗变研究装置次临界反应堆概念设计

根据中国加速器驱动嬗变研究装置(CiADS)的建设要求,完成了CiADS中次临界反应堆的概念设计。次临界反应堆为液态铅铋冷却快中子反应堆,采用半池式-半回路式的布置方式,通过主容器的中心管实现了与散裂靶在结构上的耦合。燃料组件及换料方式采用相对成熟的技术方案,设置了铅铋主冷却剂辅助系统,通过多种专设安全设施来保证反应堆的安全。CiADS次临界反应堆充分考虑了堆靶耦合界面的可实现性,利用了液态铅铋冷却剂良好的传热性,结合了池式堆冷却剂自然循环的特性及回路式堆冷却剂装量少的特性,具有良好的可行性、安全性、布置灵活性和技术扩展性。     

气泡在液态铅铋合金内上升行为的数值模拟

为利用气泡提升泵的概念设计来增加铅铋合金非等温回路的自然循环能力,需对充入回路的气泡大小进行选择。气泡的初始直径能显著影响气泡提升泵提升自然循环的能力。利用VOF模型,对不同初始直径的氦气泡在液态铅铋合金中的提升作用进行了数值模拟研究。结果表明,对于单个气泡,随着初始直径增大,提升能力呈先增加后趋于不变的趋势;初始直径较大的气泡易分裂生成较小的子气泡附着在管壁上,有影响传热效率的潜在可能。研究了在静止液态铅铋合金中,不同初始直径的氦气泡上升速度和上升高度与时间的关系及气泡分裂的原因。     

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。     

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.     

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).     

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。     

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。     

核与辐射风险的认知与沟通

面对公众对核与辐射风险极度敏感的现象,本文阐述了对风险的认知及影响认知程度的因素,介绍了风险沟通的发展阶段和四种类型,并给出了若干有效的风险沟通策略建议。     

Thermophysical and mechanical properties of CrB and FeB

ABSTRACT

Fuel debris in the Fukushima Daiichi nuclear power plant is thought to contain borides that are generated from B₄C control material. In order to successfully devise methods to effectively remove the debris material, characterization of the properties of the fuel debris is essential. This paper presents some of the thermophysical and mechanical properties of two types of borides, FeB and CrB, and compares them with those of Fe₂B and ZrB₂. These are the representative borides that might have been generated in the Fukushima Daiichi (1F) nuclear power plant accident. We observed that the thermal conductivity values of both CrB and FeB are much lower than that of ZrB₂, and are similar to that of Fe₂B. Moreover, the Vickers hardness and fracture toughness of FeB and CrB are almost identical to each other, and similar to those of ZrB₂ and Fe₂B.     

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.     

测温热电偶拔出回收技术及回收处理装置

核电站反应堆测温热电偶回收装置是堆芯热电偶检修、更换、回收的专用设备。本文结合３００ＭＷ反应堆型，介绍了一种结构简单、操作方便、使用安全可靠的热电偶拔出回收技术及回收处理装置。