含周向缺陷管道的塑性失稳失效评定的名义应力比法

提出了评定带周向缺陷塑性失稳失效的一种新方法－名义应力比法，并详细说明该方法的优点和基本思路，与ＡＳＭＥ规范许可缺陷尺寸表法相比，该方法更实用。     

核电厂调试期间核级管道振动测量工作改进

美国机械工程师协会(ASME)OM-S/G-2000 Part 3导则存在操作性不足的缺陷,而国内核电厂核级管道振动测量工作均依此导则,采用的试验方法类似,但都无法全面、准确预测管道振动极大点。以某核电厂调试期间核级管道振动测量工作为例,从试验对象的筛选、关键设备或部件的选取、测点选择、现场试验及振动分析评价5个方面进行探讨,提出改进建议,最后以某核电厂安全壳喷淋系统(EAS)的某管段振动为研究对象,对测量方法、振动限值计算及评价等进行案例分析。     

通用计算优化语言GCOL原理、实现与在管道设计中的应用

核电站初步设计时在管道力学计算中，计算结果通常不能满足规范的要求。要经过反复修改试算，最终得到满足要求的设计。将这一设计过程尽可能的自动化，是编制GCOL程序的目的。本文介绍了GCOL程序的原理，及在CAPS程序系统中的实现。并用一个例题说明了该程序在实际工程中的应用。GCOL程序可以用来辅助设计人员实现管道设计的优化。     

核级管道的布置和应力分析

核级管道系统的设计是个复杂的优化问题。本文从核反应堆管道系统的设计步骤、管系的解耦准则以及如何通过选择支撑和调整管道走向来降低应力水平等几个方面阐述了此问题。     

核设施气载放射性排放物取样的管道损失--美国标准推荐的计算方法简介

介绍了美国气载放射性排出物取样与监测标准中推荐的气溶胶粒子管道损失的估算方法,重点介绍了粒子在取样管路的入口、弯头和不同方位角的直管段中产生壁损失的计算方法及计算公式应用的注意事项。这些估算方法可编制成管道损失计算软件,正确应用估算方法和计算软件,不仅可对现有烟囱取样系统给以评价,为烟囱取样系统设计提供依据,也可能为取样系统管道损失的监测或监控提供技术基础。最后将估算方法的应用与计算结果同部分实验数据和国外的某些计算结果作了对比。     

核电厂主蒸汽管道阻尼减振与抗震分析

增设阻尼器是处理核电厂主蒸汽管道振动与地震冲击问题的主要方法。本文利用Sap2000软件建立核电厂主蒸汽管道的有限元模型,分析出了管道的固有频率、振型等动态特性。分析结果表明,平动是主要的影响振型。本文应用非线性动力时程分析计算蒸汽管道在33 Hz频率下的振动及地震响应,得到了管道加设阻尼器前后的振动位移和振动速度数据,并进行了比较,探讨了阻尼器在管道减振与抗震中的应用效果。结果表明,在不改变管道原有结构、不影响管道正常工作的前提下,安装液体黏滞阻尼器可以对主蒸汽管道产生减振与抗震的效果。     

ESPRESSO钠回路管道的应力分析和计算

由意大利引入ESPRESSO钠回路是为意大利的PEC快堆进行燃料元件考验和热冲击试验而建造的,该台架的寿命和性能已不是原始设计值。同时由于是高温设施,经过拆卸和重新安装,特别是焊接的质量和检验的标准不同,对设备的安全运行均有重要影响。本工作对ESPRESSO钠回路管道应力进行分析和计算,判断回路管道的应力分布水平,最终通过调整恒力吊架来保证回路的运行安全。     

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.     

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。     

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).