直接充电式核电池能量转换效率提高研究

通过分析直接充电式核电池的结构和工作原理,给出了直接充电式核电池等效电路.在此基础上,得到了直接充电式核电池的充电方程,及用于计算在不同负载阻值情况下输出功率的简化模型.简化模型最大理论输出功率及伏安特性曲线与Warren F.Windle实验符合很好.考虑到直接充电式核电池能量转换过程,提出了提高能量转换效率的途径:...     

具有独特用途的放射性同位素电池

放射性同位素电池是20世纪60年代发展起来的一种新型电源。由于它具有寿命长、工作可靠、对环境适应性强、不需经常维护、结构紧凑、比容量高等优点,因而在空间、陆地海上、海底以及医学领域都有独特的用途。本文分析了热电型放射性同位素电池的特点、基本原理、主要构成,介绍了热电型放射性同位素电池在空间地球卫星、月面试验站、外层星际探测以及在地面、海下、医学等方面的广泛应用,并展望了放射性同位素电池在21世纪的发展应用前景。     

月球基地核电源系统方案研究

月球基地的建立首先需解决能源供给问题,核电源系统具有功率大、寿命长、环境适应性强等优点,是月球基地及其他深空探测任务中理想的能源提供方案。本文分析了目前可用于月球基地的能源情况,有针对性地提出40 kWe月球基地核电源系统的设计理念,经初步优化设计,给出了该系统的流程和总体设计参数,并从物理、屏蔽、热工以及结构方面对系统进行了分析和论证。结果表明,该系统方案合理可行,能满足安全和寿期要求。     

β辐射伏特效应核电池的研发现状

近年来,关于β辐射伏特效应核电池的研究主要集中在放射源的选取以及新型半导体材料器件的加工工艺等方面。从能量转换机制、放射源的选择、换能器件材料的选择、电池的输出性能和能量转换效率等方面对β辐射伏特效应核电池进行了讨论和分析。最后对核电池的研究方向和应用前景进行了展望。     

核电池研究取得突破性进展

正【世界核新闻网站2014年9月18日报道】美国密苏里大学研究人员已生产出一个原型水基核电池。与现有的电池技术相比,这种电池的效率更高,能够运行的时间更长,最终可用于为汽车和宇宙飞船供电。这种电池使用的是被称为"贝塔伏特"(Betavoltaics)的电池技术,即一种利用放射性同位素的β射线来发电的技术。这种技     

一种高精度的核密度计设计与实现

为改善传统核密度计标定过程中,被测介质密度与探测器测量强度之间的线性关系,设计了一种双探测器模型的核密度计。首先基于γ射线指数衰减理论、能量较低的光子向前与向后散射概率相当的假设以及Klein-Nishina公式推导出被测物质密度计算的理论公式,建立对应的密度理论方程。然后利用蒙特卡罗软件MCNP5对双探测器模型进行仿真计算,验证上述三种理论方程的合理性。研究表明双探测器模型对改善核密度计标定方程的线性关系是有效的,其拟合系数相比于传统的核密度计而言,提升了2.4%,从而提高了核密度计的测量精度。     

世界核协会对未来核电发展的三种预测

【美国《核新闻》2005年11月刊报道】世界核协会(WNA)的一份题为《全球核燃料市场:2005—2030年供需关系》的报告对未来20年的世界核电和铀的供需关系作了预测。核电装机容量该报告指出,世界电力需求在过去30多年里的快速增长为核电的发展提供了巨大的市场发展空间,核电目前满足了世界17%的电力需求。该报告还称,核电未来的前景变得“非常光明”。该报告对未来核电装机容量的发展趋势做了从大幅增长到小幅下降的三种即乐观情景、参考情景和悲观情景的预测。美国乐观情景的预测以美国现有全部103座反应堆到2020年仍在服役为假设前提。参考…     

核蓄一体化是核电发展的新思路

要实现我国经济、社会、生态环境的协调发展,改善大气污染环境,实现两个百年目标,发展核电是必然的选择。从核电技术和经济特性方面分析,并参考诸多发达国家的核电运行模式,核电机组适合作为基荷机组运行,但电网存在峰谷差也需要调峰能力,核电作为电网中的一员也理应在调峰上做出应有的贡献。本文建议按照核蓄一体化运营模式,在规划建设核电的同时规划建设与之配套的抽水蓄能电站,充分利用核电及抽水蓄能电站各自的特点,走出一条核电协调发展之路。     

从核设备设计提升核电安全性的基本思考

针对日本福岛核事故发生及演化,提出从核设备设计方面加强核电设计安全性的思考,重点阐述了从建立先进核电标准体系、采用先进设计分析方法、形成完整试验验证体系及合理考虑"超设计基准事件"和加强核安全文化建设等方面提升核安全的重要性,对从事核电设计人员给予启示。     

Development of a beta radioluminescence nuclear battery

A nuclear battery consisting of a beta source,a phosphor layer and a photovoltaic device was prepared.Planar phosphor layers were synthesized through physical precipitation of ZnS:Cu,ZnS:Ag or SrAl_2O_4:Eu~(2+),Dy~(3+)phosphors.The radioluminescence(RL)spectra were used to analyze the RL effects of the phosphor layers under beta-particle excitation.Feasibility of using the materials as intermediate absorbers in the beta batteries was studied.TheⅠ-Ⅴcharacteristics of beta RL nuclear batteries with different phosphor layers were tested using~(63)Ni or~(l47)Pm beta sources.The output power of zinc sulfide matrix phosphor layer was better than that of rare-earth element oxides.In addition,a thin aluminum reflective layer was vacuum-evaporated on the phosphor layers to improve the efficiency of beta RL nuclear batteries,and the results were discussed.     

核电建设企业综合管理信息平台的设计与应用

核电建设企业信息化管理经过20世纪末的高速发展,完成了众多应用管理信息系统,但大多局限于单项目管理,形成一个个信息孤岛,相互之间缺乏有效的信息沟通。随着国家对核电建设的积极推进,企业充分运用信息技术对管理的各个层级进行有效整合,实现人、财、物等资源的深度开发,并不断推动组织机构的变革,使企业不断地提升管理理念以适应新的竞争环境。     

数字化核测仪表的设计与算法分析

介绍了数字化核测仪表的设计与算法分析，给出了数字化核测仪表的工作原理，以及以单片机为核心的硬件、软件的实现方法、实现准则，以及对反应堆测量的一些算法分析。     

A new paradigm for core design aimed at the sustainability of nuclear energy: The solution of the extended equilibrium state

The future expansion of nuclear energy, a technology identified as one of the main candidates for reducing the world’s dependence on fossil fuels, requires a thorough analysis of the sustainability of this energy source for long-term supply. Generation-IV nuclear systems could represent a turning point for energy production by minimizing the environmental footprint of the fuel cycle. A new paradigm is thus required for reactor design, focusing, at the core design level, on both the closure of the fuel cycle and the effective utilization of natural resources.     

适用于快速平台测井的多通道核能谱测井仪设计

介绍一种基于快速平台测井要求的多通道核能谱测井仪设计方案。复杂可编程逻辑器件的应用使仪器功能增强，规模减小。该系统可对岩性密度长短源距脉冲信号、自然γ能谱脉冲信号进行多道脉冲幅度分析，并对补偿中子测井信号及井下多路常规模拟信号、脉冲信号进行数字化采集。数据传输采用曼彻斯特编码，传输方式可选择20kB／s半双工(兼容Atlas 3508)或下行20kB／s、上行41．66或93．75kB／s全双工方式(兼容Atlas WTS)，适应挂接到不同测井系统的需要。     

Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion

Nuclear Thermal Rocket (NTR) propulsion is a viable and meritorious option for human exploration into deep-space because of its high thrust, improved specific impulse, well established technology, bimodal capability, and enhanced mission safety and reliability. The NTR technology has already been investigated and tested by the United States of America and Russia and the former Soviet Union. The representative Nuclear Engine for Rocket Vehicle Applications (NERVA) type reactors traditionally used Highly Enriched Uranium (HEU) fuels, shaped in hexagonal fuel element geometries because of the importance of making a high power reactor with a minimum size. Although the HEU-NTR designs are the best choice in terms of rocket performance and technical maturity, they inevitably provoke nuclear proliferation obstacles not only for all research and development activities by civilians and non-nuclear weapon states but also for potential commercialization. To overcome the security issues due to HEU, the non-proliferative, small-size NTR engine with low thrust levels of 41 kN–53 kN (9.2 klb_f ∼ 11.9 klb_f), Korea Advanced NUclear Thermal Engine Rocket utilizing a Low-Enriched Uranium fuel (KANUTER-LEU), is being designed for future generations. Its design goals are to make use of an LEU fuel for its fairly compact core, but to minimize the rocket performance sacrifice relative to the traditional HEU-NTRs. To achieve these goals, a new space propulsion reactor is conceptually designed with the key concepts of a high uranium density fuel with resistance against high heating and H₂ corrosion, a thermal neutron spectrum core, and a compact and integrated fuel element core design with protective cooling capability. In addition, a preliminary design study of neutronics and thermal-hydraulics was performed to explore the design space of the new LEU-NTR reactor concept. The result indicates that the innovative reactor concept has great potential, both to implement the use of an LEU fuel and to create comparable rocket performance, compared to the existing HEU-NTR designs.     

核部件非授权移动安全警戒系统方案设计

介绍了一个核部件非授权移动安全警戒系统的设计方案,讨论了核部件的移动快速检测技术和对位监测方法,提出了系统的结构组.     

基于APD阵列的PET探测器模块电子学

APD阵列γ光子探测器的诸多优点使多特别适用于PET成像技术，根据APD器件本身的特点以及PET系统对探测器模块信号读出的要求，在介绍APD实验模块前端电路的设计和性能测试以后，详细讨论了APD模块电子学的整体设计。     

Feasibility study of decay heat uncertainty reduction using nuclear data adjustment method with experimental data

The accurate prediction of the decay heat is essential, especially for nuclear power plant safety purposes. However, it is known that the decay heat predicted by nuclear fuel burn-up calculations is uncertain because of uncertainty of nuclear data employed in the calculations. If the decay heat uncertainty can be reduced, the safety margin of the predicted decay heat can also be reduced, and feasible design ranges of various types of equipments related to the decay heat can be extended. In the present study, we use the nuclear data adjustment method for the decay heat uncertainty reduction with several types of the experimental data. As a result, we clarify that the decay heat uncertainty with short- and long-term cooling periods can be reduced by this method with appropriate experimental data.     

Basic consideration of a nuclear power monitoring system using neutron-induced prompt gamma rays

ABSTRACT

Monitoring only neutron flux in a nuclear reactor core has an advantage of offering reactor power monitoring accuracy. We started the development of a new nuclear instrumentation based on the measurement of prompt gamma rays emitted from metals placed at the neutron flux monitoring positions. The thermal neutron flux at the position of each placed metal piece can be monitored by measuring the prompt gamma rays as the count rate of each energy. The gamma-ray energy range was limited from 6 to 10 MeV to mitigate the interference of environmental gamma rays. Four metals, Ti, V, Ni, and Cu, were chosen as candidates in consideration of their neutron emission rates and self-absorption. In an experiment with a high-purity germanium semiconductor detector, we considered the identification of individual peak energies in an assumed situation where prompt gamma rays were emitted from the four different metals at the same time. Energy resolutions of the peak with the largest energy gap from the nearest energy peak of the other candidate metals were smaller than the gap. Thus, we confirmed that at least one peak for each candidate metal was able to be separated from the peaks derived from other candidate metals.