Based on abundant data collection and onsite surveys,the paper summarizes major progress China has made in application of nuclear technology(ANT)in the nea-rest decade,and reviews important role of ANT in improving people's livelihood and health.The paper also details status of ANT in China and related installations,inclu-ding electron accelerator for irradiation and related technology,γ-ray source and related integrated installations and radioisotope manufacturing technology.Drawing support from case study,the paper then analyzes development of ANT and ANT related indus-tries in industry,agriculture,medicine,environment,national security,etc.By stud-ying domestic and foreign situation facing the development of ANT,the paper finally foresees prospect and trend of ANT in China.

The filled skutterudite compound PrFe4P12 exhibits anomalously phase transition and heavy Fermion (HF) state below 6.5 K.In order to investigate effects of 3d-electron on the phase transition and HF state,samples of Pr(Fe1-xCox)4P12 were synthesized to observe evolution of f-electron state by specific heat,magnetic susceptibility measurement and inelastic neutron scattering.The experiment results indicate that the properties of PrFe4P12 are very sensitive to Co doping.The ordered state and HF state are suppressed by only 3% Co substitution,and the well-localized nature of f electrons appears in the Co-substituted system.

China Advanced Research Reactor (CARR ) is an excellent platform for indirect neutron radiography (INR) .The experimental conditions of the INR at CARR were calculated and analyzed by the Monte Carlo method ,based on which the first and the second exposure time was calculated .The INR experiment was carried out with the sample of dummy fuel rods at one of the CARR’s thermal neutron beam channel ,and the methods of processing and analyzing the neutron images were also studied .

核燃料元件作为反应堆的核心部件,在极端的条件下服役会发生破损,导致核泄漏.为了保障反应堆安全运行,核燃料元件从加工、生产到服役的过程中必须进行检测,以确保安全.中子照相是对具有放射性的核燃料元件进行无损检测的独特技术.进行测试时,核燃料元件必须放置于转移容器中,实现运输及检测过程中对核燃料元件的屏蔽和运动控制.本文以核电站绿色监督区剂量要求为标准,利用蒙特卡罗程序优化计算了适合于中国先进研究堆(Chinese Advanced Research Reactor,CARR)热中子照相设备的转移容器的材料及尺寸,同时设计了用于控制元件运动的机械装置,确定了最优化的方案.该装置可满足CARR中子照相设备对长2m核燃料元件进行无损检测的要求.

中子照相可以对具有放射性的核燃料元件进行无损检测.本文采用核燃料元件模拟件在中国先进研究堆(CARR)中子束流水平孔道利用0.1mm厚的Dy中子转换屏配合工业X射线胶片获得成像,进行中子照相无损检测的模拟研究.利用检测成像发展了核燃料元件缺陷分析、包壳氢聚含量定量测量、芯块U-235富集度定量测量等成像分析方法,为真实核燃料元件的检测打下基础.

The nuclear fuel rod is a key component of nuclear plants and reactors. It works in the extreme conditions, so it is easy to be broken. In order to be safe in operation, lots of testings have to be carried out from fabricating to operating of the fuel rod. As a unique non-destructive testing technique, neutron radiography can be used to measure the nuclear fuel rods with radioactivity by an indirect neutron radiography method. Study the indirect neutron radiography method is the primary step of testing. Non-destructive testing experiments were carried out at China Advanced Research Reactor (CARR) by indirect neutron radiography method with dummy nuclear fuel rods as the samples. The 0.1 mm-thick Dy foil was used as the neutron converter. The neutron images of dummy nuclear fuel rods were obtained. The resolution of testing was analyzed with the images. Through imaging analysis methods, the structure defections, the hydrogen accumulation in the cladding and the U-235 enrichment of pellet were studied and analyzed. The indirect neutron radiography method and the neutron image analysis method were studied. The work described in this paper provides a primary guideline for investigating actual irradiated fuel rods by the neutron radiography at CARR in the future.

<正>BNCT技术的发展和应用前景比较广阔。原子能院综合优势的发挥大有可为。应该充分利用前期工作打下的基础,通过大力开展国际国内合作来提高研究工作的起点,而不必一切都从头做起,在国内的合作应该特别注意吸引有实力的医院参加。

This paper describes the experimental procedures, testing information and application advantages when neutron radiography is used for non-destructive inspections and quantitative analysis of fuel elements from nuclear power plants. Both the {sup 235}U enrichment and the material distribution inside the pellets can be determined by neutron radiography methods for the non-irradiated fuel elements. Both the structural integrity of fuel elements for different reactors such as PWR, BWR, FBTR and the hydrogen accumulation in the cladding material can be inspected for the irradiated samples. (authors)

New versions of Nuclide Guide (NG) and Chart of the Nuclides (ON) were developed as a result of Russian-Chinese collaboration. Compared to the previous versions of the NG and ON - 2006 new evaluated information has been included to the NG and ON - 2009 from the following publications: 1) Nuclear Data Sheets, volumes 107 - 110, 2) Monographie BIPM-5, Table of Radionuclides, 2006, 3) Monographie BIPM-5, Table of Radionuclides, 2008. In addition, for the Nuclide Guide-2009 the authors re-calculated the average energies of radiations of the 500 radionuclides with half-lives about and more than 1 hour. The International Chart of Nuclides was developed taking into account information added and revised in Nuclide Guide-2009. The presented decay data can be used not only in nuclear physics and associated fields but also in medicine, agriculture and space studies.

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Recent years, a lot of achievements on nuclear data evaluation and nuclear database set up et al. are obtained by China Nuclear Data Centre (CNDC). A new evaluated neutron data library CENDL-3.1, which contained 240 nuclei data file with ENDF6 format, is released and a lot of benchmark and data validation for this library have been performed.The nuclear data model study and code system improvement are clone at CNDC and some code systems (UNF, MEND et al.) based on the updated study results is being used in the evaluation activities.As an important tendency of nuclear data application, the evaluated covariance files are become more and more important, so establishment of the producing method for the covariance files is one of the most important tasks for nuclear data researchers. A new evaluation system for evaluation the covariance file is being developing and some good results are obtained at CNDC. Some good improvements on the study of fission yield data evaluation and relative field have been carried out. A new semi-empirical model, which used to analyze and to describe the yield-energy relations and a new systematics on independent yield with Zp model are developed.The progress at CNDC about nuclear data evaluation, data process, validation and related research fields studies are mentioned in this presentation.

<正>一、引言1.核能在低碳能源政策中的重要作用2000年,全世界60亿人口消耗了100亿吨标准煤;2006年,65亿人口消耗了117亿吨标准煤。预计到2050年,世界能源消耗将比2000年增加一倍。为了应对世界能源消耗的快速增长和温室气体

The updated Chinese Evaluated Nuclear Data Library CENDL-3.1 is an important achievement based on the nuclear data evaluation works in recent years, at China Nuclear Data Center (CNDC) in cooperation with China Nuclear Data Coordination Network (CNDCN). CENDL-3.1 contains the evaluated data for reactions with incident neutrons on 240 nuclides (from (1)H to (249)Cf) in energy region of 10(-5) eV - 20 MeV. All data obtained according to the evaluations of experimental data and the predictions of the nuclear reaction model calculations. For most important nuclei of this library, the benchmark testing and validations have been performed, the comparisons with other nuclear data libraries (ENDF/B, JENDL, BROND, JEF, et al.) have been done. The testing version of CENDL-3.1 is CENDL-3.0, which has been provided for China domestic users. Follow the using back feed of CENDL-3.0, a lot of improvement has been done. The CENDL3.1 is provided for all users by ENDF format and is released to the world in the end of 2009. The overview, evaluation methodology and some important results of new evaluations, benchmark testing and validations for this library will be introduced in this contribution.

The neutron total cross-sections of thulium (Tm-169) were measured in the neutron energy region from 0.01 eV to 100 eV by using the time-of-flight method at the Pohang Neutron Facility, which consists of an electron linac, a water-cooled tantalum target with a water moderator, and a 12-m-long time-of flight path. Two thulium plates with different thicknesses were used for the neutron transmission measurement. The background level was determined by using a notch-filter of Co, In, and Cd sheets. The present measurement was compared with the previous ones, while a new set of resonance parameters of Tm-169 isotope was obtained from the transmission ratio by using the SAMMY code, with a comparison with the recommended parameters by Mughabghab.

The neutron total cross-sections of thulium（169Tm） were measured in the neutron energy region from 0.01 eV to 100 eV by using the time-of-flight method at the Pohang Neutron Facility,which consists of an electron linac,a water-cooled tantalum target with a water moderator,and a 12 m time of flight path.Two thulium plates with different thicknesses were used for the neutron transmission measurement.The background level was determined by using a notch-filter of Co,In,and Cd sheets.The present measurement was compared with the previous ones,and a new set of resonance parameters of 169Tm isotope was obtained from the transmission rate by using the SAMMY code,with a comparison with the recommended parameters by Mughabghab.

Mass parameters for the relative and neck motions in fusion reactions of symmetric systems $^{90}\mathrm{Zr}+^{90}\mathrm{Zr}$, $^{110}\mathrm{Pd}+^{110}\mathrm{Pd}$, and $^{138}\mathrm{Ba}+^{138}\mathrm{Ba}$ are studied by means of a microscopic transport model. The shape of the nuclear system is determined by an equidensity surface obtained from the density distribution of the system. The relative and neck motions are then studied and the mass parameters for these two motions are deduced. The mass parameter for the relative motion is around the reduced mass when the reaction partners are at the separated configuration and increases with a decrease of the distance between two reaction partners after the touching configuration. The mass parameter for the neck motion first decreases slightly up to the touching configuration and then increases with the neck width, and its magnitude is from less than a tenth to several times more than the total mass of the system. The mass parameters obtained from the microscopic transport model are larger than the ones obtained from the hydrodynamic model and smaller than those obtained from the linear response function theory. The mass parameters for both motions depend on the reaction systems, but the one for the relative motion depends on the incompressibility of the EoS more obviously than that for neck motion.

The minimization of the nuclear waste is the key problem for the long term and sustainable nuclear energy development.Accelerator driven system (ADS) is a kind of high efficient nuclear waste transmutation machine (or incinerator), which is the key technique to solve the nuclear water problem. The basic theory of ADS and driven influence of ADS on the advanced accelerator, advanced cooling technique, etc are introduced. Meanwhile the present research situations of ADS in some countries are compared. At last,the key problem of the ADS development and the relationship between ADS and the development of nuclear energy in China is discussed.

身为中国核工业集团公司唯一一位人大代表,科研院所出身的赵志祥一贯低调。但或许是今年核工业发展的大好形势使然,一向低调的赵志祥也有了非常表现,以下两个数字或许能给予形象的说明:4个建议案:在今年提交的4个建议案中,除核电发展技术、核科技应用两方面主体内容外,对于此次两会议题之一的"医疗改革",赵志祥也结合核工业领域的实际特点表达了自己的意见。2篇文章:今年,赵志祥面对媒体也显得十分热情。在科技日报等多家中央媒体争相转载的两篇稿件中,他兴奋地传达"核电快堆技术预计2030年投入商用"的信息,并从容而笃定地表达"离开能源产业难谈经济可持续发展"的观点。