中子活化分析对河南南阳独山玉的研究

应用中子活化分析法对河南南阳独山玉的稀土微量元素进行了研究 ,结果表明 :白独玉、绿独玉与黑独玉的地球化学特征有明显的差别。其中 ,它们每种玉的平均值 :8个稀土总量 (8∑REE)分别为 1.4 5、6 .895、3.86 7μg·g- 1;全线斜率 (La/Yb)分别为 14 .2 77、4 .936、0 .84 9μg·g- 1;微量元素Sr分别为 75 4、4 34、115 μg·g- 1,Cr分别为 5 .5 3、10 95、85 1μg·g- 1,Fe分别为 2 777、2 838、2 875 0 μg·g- 1,Mn分别为 6 8、6 5 .5、5 32 μg·g- 1;绿独玉正Eu异常最大 ,而黑独玉的正Eu异常最小。这些特征可作为鉴别独山玉的地球化学标志 ,对考古及古玉的深入研究与鉴别具有重要意义。     

玉华山火山盆地铀矿床为山—筒山断裂带控矿特征

在简述玉华山地区地质背景的基础上,阐明为山—筒山断裂带地质特征,分析其对铀矿控制特点,总结铀矿化富集规律。认为为山—筒山断裂带不仅是玉华山火山盆地控岩构造,而且是重要的控矿、导矿和容矿构造。控矿构造可划分为:主构造对矿化的控制、旁侧次级构造对矿化的控制和主构造与岩性组合对矿化的控制3种形式。铀矿化富集一方面与断裂构造发育程度有关;另一方面与断裂构造充填物关系密切,特别是与充填于断裂带中花岗斑岩形态及产状变化密切相关。今后玉华山地区铀矿找矿工作,可把控矿构造作为主要研究目标。     

简析核电厂安全级连续工作制电动机的鉴定

文章对核电厂安全级连续工作制电动机的鉴定目标、服役环境条件、鉴定寿命、老化分析、设计基准事件模拟试验、状态监测等鉴定要素进行了系统化阐述,并对鉴定方法和鉴定程序进行了总结,可以为鉴定单位编制具体的安全级连续工作制电动机鉴定规程和开展具体的鉴定活动提供有效指导。     

核安全级电缆鉴定寿命的分析再评估技术

基于对安全级电气设备（1E设备）鉴定方法和鉴定寿命的分析和研究,将分析再评估技术应用于核电厂有环境鉴定要求的电缆（EQ电缆）的寿命评估,可在满足安全要求的前提下合理地延长EQ电缆的鉴定寿命,确保电缆在鉴定寿命的延长期内仍然能够按照规范的要求实现其预期功能。该方法不仅可用于核电厂正常运行期间电缆合格鉴定状态的评估,也可用于电缆在核电厂运行许可证延续（OLE）期间实现其预期功能的能力评估,该方法在国内核电厂已有实际应用。     

压水堆核电站严重事故下的设备鉴定

本文给出了压水堆核电站严重事故下设备鉴定研究的基本内容和研究结果。对需鉴定设备的确定原则,鉴定环境条件包括压力、温度及辐照剂量的确定方法,以及设备鉴定建立的过程进行了详细的讨论和分析。        

用X射线荧光分析法对珍贵邮票进行快速鉴定的技术

在有关邮票鉴定实验结果的基础上,编写了Ｘ射线荧光分析技术对珍贵邮票快速鉴定的在线分析程序,该程序将测量,数据获取,判别分析,邮票数据库调整等工作集中在一起,在测量的同时可完成数据获取和判别分析等工作,使得分析判别工作在测量过程中完成,并将判别结果及时反馈,以便测量者决定测量工作的进行与否,使鉴定结果在尽可能短的时间内给出,从而使得鉴定技术趋于实用化。     

核电厂数字化仪表控制系统设备鉴定方法研究

探讨核安全级数字化仪表控制系统(DCS)设备鉴定的标准体系架构和总体要求。通过对NUREG0800和RCC-E技术规范的对比,分析适用于我国国情的核安全级DCS设备鉴定技术,研究通用的鉴定标准体系和方法,并提出相应验收准则。     

热力环境条件分析法鉴定研究

本文根据温度对于设备性能影响的两种效应,总结了采用分析法开展热力环境条件鉴定时需要考虑的鉴定因素,并据此设计了一种用于热力环境条件分析法鉴定的鉴定流程。基于Arrhenius公式编写了热力环境条件分析法鉴定用热老化效应计算程序,分析了计算程序中的微分步长和活化能的取值对热老化效应包络性判断的影响。计算程序不仅可以用来进行分析法开展热力环境条件鉴定时热老化效应包络性判断,还能用于指导补充证明材料或试验进行进一步的热老化效应包络性分析。     

AP1000核电站主控室盘台抗震鉴定试验研究和工程实践

抗震试验是设备鉴定的一部分,AP1000核电设备的抗震鉴定相比于传统抗震鉴定有了新的要求和方法。为满足AP1000核电设备的抗震鉴定要求,本次试验与传统抗震试验有所不同。本文以完成的主控室盘台抗震试验为例,介绍和分析该试验在反应谱、加速度计布置、功能性测试等方面的特殊要求。试验结果表明主控室盘台满足AP1000抗震鉴定的要求。这些特殊要求不仅可保证很好地鉴定试验件的结构完整性和安全功能性,而且能发掘其设计裕量。     

大型钠冷快堆设备鉴定特点及分析

本文首先从法规层面指出实施大型钠冷快堆设备鉴定的必要性;其次,通过鉴定标准、设备特点、环境条件、鉴定技术以及试验设施等方面的对比,阐述了大型钠冷快堆与压水堆设备鉴定之间的差异性;针对两者存在的差异性,以及中国实验快堆建设过程中设备鉴定技术积累的有限性,从鉴定标准体系建立、钠环境设备失效机理研究、大型堆容器抗震试验研究、钠环境试验设施研究以及大型钠冷快堆设备鉴定数据库建构等方面进行了分析,并给出了建议。     

福泉山良渚文化玉器的PIXE分析

报道用质子激发X荧光技术（PIXE）分析福泉山良渚文化玉器的实验结果。采用PIXE方法可以可靠地鉴别福泉山玉器的种类,福泉山玉器中有软玉、也有岫玉。它们与江苏溧阳小梅岭玉在元素含量上差别很大,但软玉与新疆和田出产的软玉很类似。分析福泉山软玉铁镁占位比S,可排除杂质元素干扰,得到矿物结构和沁色信息。     

用质子激发X荧光分析技术鉴别玉器种类

质子激发Ｘ荧光分析中以测定玉器的主量、次量及微量元素的成分和含量,因而可以将那些外形及颜色相近的玉器因其化学组分的不同而清楚地分开,并得知其真实的材料种类。对于主要化学组分一致的同类玉器,如果产于不同的地方,则由于其成矿地区地球化学环境的不同,它们的微量元素种类及含量也将有所不同,因而这一方法也可用来判定玉器的产地。     

玉石及中国古代玉器的PIXE分析

本文用外束PIXE技术分析了中国古代玉器和玉石的主量、微量元素的种类和含量.实验结果表明,外束PIXE技术在判定古代玉器的玉料来源和区别不同产地玉石方面具有广阔的应用前景.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

Design features and thermal margin assessment of core protection and monitoring systems of an integral reactor,SMART

The Korea Atomic Energy Research Institute has developed the SMART integral reactor, and SCOPS and SCOMS were also newly developed as advanced real-time core protection and monitoring systems for SMART. SCOPS calculates the minimum DNBR and maximum LPD based on several on-line measured core state parameters, and SCOMS calculates the limiting conditions for operation variables and assists the operator in implementing the technical specification requirements for monitoring. The design features and characteristics of SCOPS and SCOMS were described. The performance of the SCOMS power distribution synthesis method was evaluated and shows negligible power distribution synthesis errors. A technically reliable uncertainty analysis method was developed, and a preliminary uncertainty analysis was evaluated. The overall analysis results are similar or more improved compared to those of cycle 1 for Younggwang units 3&4 of Korea. In particular, uncertainty factors of SCOMS are much improved because of an improvement in the power distribution synthesis and DNBR calculation algorithm. Finally, thermal margins were estimated, and the DNB overpower margin of SCOMS is large enough to accommodate a 40% required overpower margin and 15% top-tier requirement thermal margin.     

Developments and needs in nuclear analysis of fusion technology

Nuclear analyses provide essential input to the conceptual design, optimisation, engineering and safety case of fusion technology in current experiments, ITER, next-step devices and power plant studies. Calculations are intricate and computer-intensive, typically requiring detailed geometry models, sophisticated acceleration algorithms, high-performance parallel computations, and coupling of large and complex transport and activation codes and databases. This paper reports progress on some key areas in the development of tools and methods to meet the specific needs of fusion nuclear analyses. In particular, advances in the production and modernisation of reference models, in the preparation and quality assurance of acceleration algorithms and coupling schemes, and in the evaluation and adaptation of alternative transport codes are presented. Emphasis is given to ITER-relevant activities, which are the main driver of advances in the field. Discussion is made of the importance of efforts in these and other areas, considering some of the more pressing needs and requirements. In some cases, they call for a more efficient and coordinated use of the scarce resources available.     

海水提铀技术最新研究进展北大核心CSCD

天然铀是保障国家核能持续稳定发展的重要物质基础。海洋蕴含有丰富的天然铀资源,从海水中提取铀,对于补充完善我国铀供应体系,实现天然铀供应自主化具有重要战略意义和经济意义。本文综述了近年来海水提铀技术研究方向的最新进展。主要总结了国内外海水提铀吸附材料、海试试验等研究结果,并对未来海水提铀工程化发展进行了展望。     

The kinetics of alpha-decay-induced amorphization in zircon and apatite containing weapons-grade plutonium or other actinides

Zircon and apatite form as actinide host phases in several high-level waste forms and have been proposed as host phases for the disposition of excess weapons-grade Pu and other actinides. Additionally, closely-related structure types appear as actinide-bearing phases among the corrosion products of spent nuclear fuel and high-level waste glasses. Self-radiation damage from -decay of the incorporated Pu or other actinides can affect the durability and performance of these actinide-bearing phases. For both zircon and apatite, these effects can be modeled as functions of storage time and repository temperature and validated by comparison with data from natural occurrences. Natural zircons and apatites, with ages up to 4 billion years, provide abundant evidence for their long-term durability because of their wide spread use in geochronology and fission-track dating. Detailed studies of natural zircons and apatites, ²³⁸Pu-containing zircon, a ²⁴⁴Cm-containing silicate apatite, and ion-irradiated zircon, natural apatite and synthetic silicate apatites provide a unique basis for the analysis of -decay effects over broad time scales. Models for -decay effects in zircon and apatite are developed that show -decay of Pu and other actinides will lead to a crystalline-to-amorphous transformation in zircon, but not in apatite, under conditions typical of a repository, such as the Yucca Mountain site.     

Comparison of Investment and Related Requirements for Selected Hydrogen Vehicle System Pathways

A model was developed for production, transmission, delivery, and consumption of hydrogen for large-scale systems ultimately providing shaft-work for hydrogen-based vehicles. (See Glossary, after References). Presently, the supply technologies are limited to solar photovoltaic, wind, nuclear, and nuclear thermochemical sources. Transmission technologies include electric power, hydrogen pipeline, and liquid hydrocarbon pipeline. Delivery technologies include both liquid and gaseous hydrogen and liquid hydrocarbon. Storage modes were selected as appropriate for the pathway transmission and delivery modes. Finally, consumption technologies are fuel-cell based, with and without a fuel processor (reformer). Overall, there were 39 separate pathways in this initial analysis. Subsystem efficiencies, capital costs, and capacity factors were derived from a literature search and supported by calculations where necessary. Overall systems efficiency, system peak power capital costs, and systems average power capital costs were calculated to indicate the potential capital investment requirements. The model was exercised to assess the capital cost (and related aspects) requirements to provide the equivalent automobile shaftwork of eleven million barrels of oil per day by the year 2040 (the Administration's objective). These costs range from $650 billion to $11.7 trillion and primarily depend on the selected energy source. The results reveal that nuclear thermochemical systems based on liquid hydrocarbon transmission and delivery lie at the low-cost end of the range, followed by nuclear or wind electric, then nuclear or wind hydrogen pipeline, and finally by solar electric and solar hydrogen pipeline. It is noted that thermochemical systems based on liquid hydrocarbons was the least-cost option for all of the energy sources. One vehicle storage technology, chemical hydride, was determined to be too costly to be included for later analysis. The results were compared against what might be expected of fusion energy. It was found that fusion hydrogen plant capital costs did not compete with Nuclear or Wind (but did with current Solar Photovoltaics) unless fusion plants were very large. The model is planned to be expanded to include coal-based hydrogen production (with CO₂ sequestration) and extended to calculate the total cost of energy delivered to the wheels.     

Enhancement of cold fusion reaction rates

Although major controversy still remains as to the source of the excess thermal power output reported from diverse successful cold fusion calorimetry experiments, considerable independent evidence does exist that low-level, deuterium fueled, cold fusion reactions can occur based upon reported neutron and tritium measurements. Because the specific fusion power output may be very low in present cold fusion experiments, there are numerous features and conditions associated with cold fusion experiments which might enhance fusion reaction rates.The principal focus of attention in enhancing cold fusion reactions occurring in an electrolytic cell is the palladium cathode where deuterium is preferentially absorbed into the cathode. The cathode's physical, metallurgical, and chemical characteristics such as purity, lattice cell size and orientation, chemical and hydrodynamic properties, and its electrical surface conditions and prevailing reactions are known to be important for maximizing deuterium loading. Even the geometrical size and configuration of the cathode and the crystalline grain size and conditioning are apparently important. The composition, pH, flow of the electrolyte, electrolysis employing rapidly time varying electrical potential and current and very high pressure and low temperature operation may also enhance fusion reaction rates.