^239Pu,^241Am,^99Tc和^137Cs在高压实缓冲材料中的扩散系数

本文从物质的一维非稳态扩散规律出发，在常温，纯氮条件下，测定了＾２３９Ｐｕ，＾２４１Ａｍ，＾９９Ｔｃ和＾１３７Ｃｓ在作为高放废物深地质处置库缓冲材料的高压实钠质膨润土中的扩散系数，９０ｄ的实验测定结果表明，在膨润土的干密度为１．９ｇ／ｃｍ＾３时，＾２３９Ｐｕ，＾２４１Ａｍ扩散系数为在１０＾－１５ｍ＾２／ｓ，＾９９Ｔｃ约为１０＾－１３ｍ＾２／ｓ，而＾１３７Ｃｓ约为１０＾－１２ｍ＾２／ｓ，都随缓冲材料     

α能谱法测定Pu材料中^241Am／Puα活度比

文章介绍用α能谱法测定Ｐｕ材料中＾２４１Ａｍ／Ｐｕα活度比的原理、方法及结果，该测定结果与用ＮａＩ（ＴＩ）γ能谱法测定的结果相一致。     

双源两次X射线荧光测量法鉴定金饰品质量

介绍了用放射性同位素Ｘ射线荧光分析法检查了２４Ｋ金饰品质量的简便方法，该方法使用＾２４１Ａｍ和＾２３８Ｐｕ两种辐射源进行两次测量。     

用两种人体胸腔模型对超铀元素活体测量系统刻度的结果及其比较

本文报道用ＬＬＮＬ胸腔模型和ＪＡＥＲＩ躯干模型对由双层晶体探测器构成的超铀元素活体测量系统进行效率刻度的结果及其比较，实验结果表明中国用ＪＡＥＲＩ模型得到的肺中＾２４１Ａｍ的诸数效率比ＬＬＮＬ模型的高７％～１０％，而对肺中＾２３８，２３９Ｐｕ用ＬＬＮＬ模型得到的计数效率比用ＪＡＥＲＩ模型的高７％－２０％。     

α谱的分析方法及应用

选取了２个能准确表达用半导体α谱仪的峰形函数。推荐了一种用二重峰α谱获取峰形参数的方法，采用麦夸脱方法计算非线性参数。建立了一个多重峰α谱分析程度ＭＵＬＴ，计算了＾２４４Ｃｍ和＾２４１Ａｍ在衰变中发射的α粒子辐射几率以及钚样品中＾２４０Ｐｕ与＾２３９Ｐｕ的原子数比。并用一个标准谱检验了它的分析准确度。     

Pu在不锈钢基底上的电沉积

对在不锈钢基底上用电沉积法制备＾２３９Ｐｕ（α）参考源作了详细研究。试验中选择ＮＨ４Ｃｌ－ＨＣｌ体系，观察了铵盐浓度、电解质酸度、电解质体积、电流密度、电镀时间、不锈钢基底材料和单面电解槽尺寸对＾２３９Ｐｕ电沉积率的影响，从而确定了最佳工艺条件，并已用于＾２３９Ｐｕ（α）参考源的批量生产中。该电镀工艺的优点是简便、快速，且获得的镀层均匀、牢固。该工艺也已成功地用于制备＾２４１Ａｍ（α）源和＾２４４     

用超铀核素复制骨肉瘤模型

本实验用７４８只ｗｉｓｔａｒ大鼠进行超铀核素２４１Ａｍ、２３９Ｐｕ、２３８Ｐｕ和２３７Ｎｐ复制肿瘤模型的研究。动物分成（１）２４１Ａｍ中毒组，２０８只，中毒剂量为０．７５×１０～３１．４５×１０４Ｂｑ·ｋｇ－１；（２）２３９Ｐｕ中毒组，１４５只，中毒...     

PWR（U）乏燃料中超铀元素在混合堆快裂变包层内嬗变研究

从中子学角度对ＰＷＲ（Ｕ）乏燃料中的超铀元素（２３８Ｐｕ，２３９Ｐｕ，２４１Ｐｕ，２４１Ａｍ，２４３Ａｍ，２３７Ｎｐ，２４４Ｃｍ）在聚变－裂变混合堆快裂变包层内嬗变的可行性进了研究。利用一维中子输运和燃耗计算程序ＢＩＤＥＣＡＹ译不同燃料组分的四个快裂变包层进行分析计算。结果表明，在聚变－裂变混合堆快裂变包层内安全，高效地嬗变ＰＷＲ（Ｕ）乏燃料中的超铀元素是可能的。     

受热中子辐照的钚样品中^242cm／^241Am活度比的测定

研究了测定受热中子辐照的钚样品中＾２４２ｃｍ／＾２４１Ａｍ放射性活度的两种方法，并将其成功地应用地下该试验样品的分析中。     

脉冲堆^241Am—Be中子源堆内使用寿命的计算方法

本文导出堆内＾２４１Ａｍ－Ｂｅ中子源＾２４１Ａｍ和＾２４２Ｃｍ核数随时间变化的计算公式并予以验证。用此公式，可从源强的角度对该源的堆内使用寿命作出合理的估计。     

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。