核安全文化与核安全监管

系统回顾和总结了核安全文化的发展进程及其阶段特征,分析了核安全文化的内涵特性。总结了我国核安全监管取得的成就,剖析了核安全监管面临的挑战和存在的问题。重点研究了核安全文化与核安全监管的关系,两者既有本质的区别,又有密切的联系。核安全监管要引入核安全文化理念,注重人文关怀,提高文化含量,提升核安全监管的层次和效率。核安全监管当局必须加强核安全文化的培育,指导核安全文化的发展。发挥核安全文化的作用。     

Study of Nuclear Physics for Nuclear Fusion

Based on the concept of damp matching [1] and the famous d + t fusion data, a conventional quantum mechanics calculation shows that the plasma fusion, muon-catalyzed fusion, and the low-energy nuclear reaction are essentially same in the sense of resonant tunneling through the Coulomb barrier. The good agreement between theory and experimental data justifies the selectivity in resonant tunneling, which implies the possibility of having fusion energy with no strong neutron and gamma radiation.     

核取证在核反应堆特征分析中的应用

以燃料栅元模型和3维燃耗计算程序MCCOOR为基础,对5 MW石墨气冷堆慢化材料、燃料元件的核素成份进行了数值模拟分析。通过核素关联分析该反应堆的特征,验证了慢化剂中~(14)C、~(10)Be含量可标识总中子通量特征,燃料元件主要放射性裂变产物~(144)Ce、~(134)Cs、~(147)Pm、~(154)Eu、~(90)Sr、~(137)Cs可标识后处理时间及次数特征,燃料核素比值可标识堆型特征。分析表明,在去核化核查核取证时,可采样分析石墨慢化剂~(14)C、~(10)Be的含量确认该反应堆的主要运行历史,也可通过分析后处理池主要放射性裂变产物含量,确认后处理的次数。在防扩散核取证时,分析材料核素比值n_(238_(Pu))/n_(pu,total)与n_(242_(Pu))/n_(240_(Pu))和可判断材料的生产堆型,以缩小被截获材料的来源范围。     

福岛核事故后核电厂核应急管理探讨

福岛核事故,对全球核电行业产生了巨大的影响,世界各国及相关国际机构进行了深刻的反思。我国也出台了多项整改措施,出版了很多文件,加强核应急管理。本文结合自身工作实践,就整改后核电厂核应急工作关注的问题进行分析、探讨,供核应急从业人员参考。     

核燃料

在法国核然料工业组织中,法杰马公司主要销售燃料组件。法比燃料公司(FBFC)的3个从属工厂都负责燃料组件的制造,该公司每年生产装铀量为1500t 的燃料组件。自1985年以来,法杰马公司又销售先进燃料组件(AFA)。该 AFA 的主要特点是使用了锆合金定位格架和可拆式上、下管嘴。大亚湾核电站要用的燃料组件正是该种与一般组件不同的先进燃料组件。法杰马公司采用钆作可燃毒物,以保证燃料组件的良好特性。近来该公司又推出混合氧化物燃料组件(MOX)。由于法杰马公司在设计和制造的各阶段都严格遵守了质量保证和质量控制制度,所以其产品质量优良、可靠性好。展望未来,法杰马公司将与法国核燃料工业中的其它集团一起,努力为用户提供尽可能好的产品。     

Nuclear fission

Nuclear fission is reviewed. The value of a channel analysis is noted in determining fission cross sections, fluctuations in fission widths and fission asymmetry. The importance of barrier height in any fission mode is emphasized. The difficulty of obtaining the mass distribution of fission fragments by a statistical theory is noted; this situation arises because the result is a strong function of the deformation factors of the fragments.Expanded version of a report to the International Conference on Nuclear Reactions at Amsterdam, July, 1956.The speaker wishes to express his gratitude to A. Bohr, D. Hughes, R. Leachman, A. Pappas, V. Sailor, W. Swiatecki and other colleagues for valuable discussions.     

大亚湾核电站核燃料的采购管理

本文介绍核电站核燃料采购各循环市场状况和主要特点 ,并结合广东大亚湾核电站的实例阐述核电站核燃料采购的合同模式和管理要点     

核电厂选址阶段的核安全监督

根据核电厂选址程序以及相关的规范标准，结合前一时期核电厂选址．分析了核电厂选址阶段核安全监督的方式和特点，并对当前监督存在的问题进行了讨论。     

核数据评价与中国评价核数据库CENDL

核数据是核基础研究、核能开发与利用以及核技术发展的基础数据,是连接核物理基础研究与核工程和核技术应用的重要桥梁,在国防与国民经济建设以及核科学发展领域起重要作用。核数据评价建库与检验是核数据研究过程中的两个重要部分,是核数据应用于核工程必不可少的环节。本文介绍了核数据内涵、核数据研究意义以及国内外核数据评价研究的简要发展历史,并结合中国评价核数据库CENDL的研究过程介绍了实验数据调研与分析评价、核数据理论模型计算、核数据统调建库与核数据宏观检验的主要评价核数据研究过程,以及我国自主建立的核数据评价方法和技术、模型及计算程序、评价数据建库和评价数据库的检验方法;介绍了基于我国自主建立的核数据评价建库与检验系统而研制的中国评价核数据库最新版CENDL 32以及对其进行的相关基准检验及应用结果;最后简要介绍了CENDL 32在反应堆屏蔽设计以及压水堆、高温堆等方面的实际应用以及与其他主流评价核数据库的比对结果。     

核爆炸的核监测技术的发展

本文阐述了核电子学与核探测技术学科中的一个重要专业分支——核爆炸的核监测技术的内涵和范围,介绍并分析了核爆监测及核辐射监测的技术要求特点和发展现状。     

核事故与国内现役核电机组核安全措施

根据核电厂核安全和辐射安全的设计防御准则,对核电史上三次重大事件进行分析,挖掘出核电事故主要因素：人因因素和超过设计值的自然灾害。同时结合国内核电厂的设计参数和运行参数,对发生类似事故进行研究比较,提出必要的预防方案。国内现役核电厂在运行安全技术上,已经可以充分预防人因事故的发生,对于超过设计值的自然灾害及外在因素引起的事故,还应重新考虑安全标准。核电厂在建设和运行过程中,需要充分考虑在极端环境下,如何将核辐射和泄漏的危害程度降低至政府以及公众能够接受的水平。     

Innovative Nuclear Energy Systems and the Future of Nuclear Power

There is a renewed interest in nuclear power worldwide. The interest is sparked by concerns about global warming and security of energy supplies. In addition to the growing interest in building more reactors in countries that already have nuclear power, future demands for nuclear power are likely to include applications in countries that do not presently use nuclear power and applications beyond large-scale electricity generation. This paper will discuss some of the characteristics that future reactors will need to have to meet such demands, as well as other measures required to facilitate a nuclear renaissance. In addition, the emergence of new international nuclear initiatives and their potential roles will be described.     

Current-Sensitive Nuclear Instrument

The radiation detector is by nature a current generator of high output impedance.

A current sensitive amplifier of low input and high output impedance can be devised for incorporation in a nuclear electronic system, providing a matched impedance at the terminal of the detector cable.

The amplifier output is given by i×Ai (i: detector current output pulse, Ai: current amp. gain), when the amplifier rise time (t _r ) is faster than the current pulse rise time. Meanwhile, when t _r , is longer than the current pulse width, the output should be defined by Q/t _r ×Ai (Q: detector output charge) in amp/coulomb units.

The rise time of fission counters, BF₃ counters, PR gas-flow proportional counters and inorganic scintillators with conventional photomultipliers is short and is even shorter in the case of fast photomultipliers combined with organic scintillators and semi-conductor detectors.

Thus marked improvement in signal-to-noise ratio can be expected from a current-sensitive system, and this has been proved even with a slow amplifier (t _r =200 ns), not to mention what can be expected with a faster amplifier (t _r <20 ns).

G-M tubes are inherently, slow, and combination with slow amplifiers does not distort the current pulse shape.

Current pulse transmission via. cable is more rational and easier than the conventional voltage pulse transmission. In the present study, G-M tube current pulses were successfully sent over a distance of 1 km without any preamplifier or pulse transformer.     

Nuclear propulsion systems

The main results of the work done at the Research and Design Institute of Electrical Technology on the development of designs and the creation of nuclear steam-producing systems (SPS) for propulsion are presented: the SPS VM-A for the first Soviet nuclear powered submarine, the SPS V-5 for the most powerful and fastest submarine with design 661 in the world team, and the designs of the first SGS MBU-40 with an integrated reactor. The basic technical solutions incorporated in the design of an integrated reactor for an advanced steam generating system are described. __________ Translated from Atomnaya énergiya,Vol. 103, No. 1, pp. 40–44, July, 2007.