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Sample records for ciae

  1. Supervisory Monitoring of Workplace at CIAE in 2011

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    1 Introduction Based on The Routine Monitoring Programme for Workplace at CIAE in 2011 which approved by Division of Safe and Environmental Protection, a management sector of China Institute of Atomic Energy (CIAE), supervisory monitoring of

  2. Safeguards technology research and development at CIAE

    International Nuclear Information System (INIS)

    Full text: China Institute of Atomic Energy (CIAE) is a multi-disciplinary institute under the leadership of China National Nuclear Corporation (CNNC). The Laboratory of Technical Research for Nuclear Safeguards was established at CIAE in 1991 to develop safeguards technology and to provide technical assistance to competent authorities for nuclear material management and control, which became one of the key laboratories approved by CNNC in 1993. The main research works for safeguards at CIAE include: nuclear material control and accounting, facilities license review and assessment, domestic inspection, NDA and DA analysis, physical protection and technical training. Research and development of equipment and technique for safeguards has been continuing at CIAE. A variety of NDA equipment that has different resolution and analysis capability has been developed. Method of NDA measurement has been investigated for nuclear material with different characteristics. Mathematics method such as Monte Carlo simulation is applied in NDA. Advanced destructive analysis (DA) instrument is installed at laboratory of CIAE, such as TIMS, ICP-MS and electronic chemistry analyzing system. The high accuracy results of element analysis and isotopic analysis for nuclear material can be obtained. It is possible to measure the types and quantities of nuclear material in a given area by means of NDA and DA. Physical protection system has also been developed. It consists of access control and management, various alarm (including perimeter alarm, intrusion alarms, fire alarms), video and audio monitors, intercommunication set and central console. The system can meet technical requirement for safeguards of first rank. Nuclear material accounting is an important aspect of safeguards research at CIAE. The computer software related to material accounting has been developed. It is the important task for scientists at CIAE to design and review nuclear accounting systems in various facilities. For

  3. Supervisory Monitoring of Workplace at CIAE in 2013

    Institute of Scientific and Technical Information of China (English)

    WANG; Li-jiao; WANG; Shao-lin; SHAO; Ming-gang; ZHAO; Yang; DU; Li-yun

    2013-01-01

    1 Introduction Based on The Routine Monitoring Programme for Workplace at CIAE in 2013 which approved by Division of Safe and Environmental Protection,a management sector of China Institute of Atomic Energy(CIAE),supervisory monitoring of radiation workplace in the supervised area of CIAE was carried out by Site Group of Radiation Monitoring and Assessment Research Section,Department of Radiation Safety.

  4. The cyclotron development activities at CIAE

    Science.gov (United States)

    Zhang, Tianjue; Li, Zhenguo; An, Shizhong; Yin, Zhiguo; Yang, Jianjun; Yang, Fang

    2011-12-01

    The cyclotron has an obvious advantage in offering high average current and beam power. Cyclotron development for various applications, e.g. radioactive ion-beam (RIB) generation, clean nuclear energy systems, medical diagnostics and isotope production, were performed at China Institute of Atomic Energy (CIAE) for over 50 years. At the moment two cyclotrons are being built at CIAE, the 100 MeV, CYCIAE-100, and a 14 MeV, the CYCIAE-14. Meanwhile, we are designing and proposing to build a number of cyclotrons with different energies, among them are the CYCIAE-70, the CYCIAE-800, and the upgrading of CYCIAE-CRM, which is going to increase its beam current to mA level. The contribution will present an overall introduction to the cyclotron development activities conducted at CIAE, with different emphasis to each project in order to demonstrate the design and construction highlights.

  5. Some techniques for sodium removal in CIAE

    International Nuclear Information System (INIS)

    In this paper the experiment and application on sodium removal and sodium disposal are presented. Steam-nitrogen process was used in CIAE for cleaning cold traps, sodium vapor traps, a sodium tank. Atomized water-nitrogen process was used for cleaning dummy fuel assembly for CEFR and a sintered stainless steel filter. Sprinkle process was used for cleaning some tubes. Bultylcellosolve was used for cleaning sintered stainless steel filter and sodium flow measurement device. Ethanol alcohol was used for cleaning electromagnetic pump. Paraffin, transformer-oil or their mixture was used for cleaning sodium valves, a sodium vapor trap and sodium-potassium alloy absorber. A small sintered stainless steel filter was distillated in vacuum. A simple sodium disposal device has been served for several years in CIA.E. It can dispose about 10 Kg sodium each time and the disposal process is no-aerosol. It operates in open air for non-radioactive sodium. In recent years a small sodium cleaning plant has been built. It can use atomized water, steam or organic alcohol to removal of sodium. The LAVEL cleaning plant and SLAPSO cleaning plant were introduced from Italy. And CEFR preliminary design on sodium cleaning for spent fuel assembly and on sodium removal-decontamination for large reactor components is introduced. Vapour-nitrogen process is planned to use in them. (author)

  6. The environment radiation capacities in the area of CIAE

    International Nuclear Information System (INIS)

    The authors mainly introduce the meaning of the environmental radiation capacities and the methodologies of determining them, the environmental radiation capacities of each of the environmental elements (atmosphere, surface water and groundwater) and the total environmental radiation capacities in the area of CIAE have been estimated by all-path-ways methods. This work will provide the scientific evidences to draft the long-term developing plans and to arrange the new facilities reasonably for CIAE

  7. Experience in radioactive waste management of research centre-CIAE

    International Nuclear Information System (INIS)

    China Institute of Atomic Energy (CIAE) is the birthplace of China nuclear science and technology and the important base for nuclear science and technology implementing pioneering, basic and comprehensive studies. The major tasks and activities of CIAE are: (1) Fundamental research of nuclear science and technology; (2) Research and development of advanced nuclear energy; and (3) Application of nuclear technology. CIAE is equipped with three research reactors (15MW heavy water reactor, 3.5MW light water swimming pool reactor, 27kW neutron source reactor), four zero-power facilities, eleven accelerators, hot cells and a lot of glove boxes which produce various kinds of radioactive wastes. CIAE pays great attention to the safe management of radioactive waste. Many measurements were and are adopted. CIAE carries out the national policy of radioactive waste management and the international fundamental principles of radioactive waste management. To protect human body and environment both now and future generation minimizes the releasing amounts and activity, minimizes the solidified wastes to be disposed of. The principles of 'controlled generation, categorized collection, volume-reduction immobilization, reliable package, in-situ storage, safe transportation and disposal' are followed in managing LLW and ILW. The liquid wastes are separately treated by precipitation, evaporation, ion exchange or adsorption by organic or inorganic materials. The spent organic solvents are treated by incineration at a special incinerator. The low level radioactive gases and liquids can be discharged into the environment only when they are clean-up and permissible level is achieved. Such discharge is controlled by two factors: total discharge amount and specific activity. The solid wastes are separately collected in site according to their physical properties and specific activity. The storage waste is retrievable designed. The spent/sealed radiation sources are collected and stored with

  8. The Present Status and Future Potential Applications of RRs in CIAE

    International Nuclear Information System (INIS)

    China Institute of Atomic Energy (CIAE), as the comprehensive nuclear research basis of China, was founded in 1950 as the birthplace of Chinese nuclear science and technology. CIAE made great contributions for the establishment and development of nuclear science the technology in China. CIAE is situated southwest of Beijing and 40 km away from the center of Beijing City. Currently, it has 3200 staff members, including 700 senior scientists. (author)

  9. Neutron activation cross section measurements and evaluations in CIAE

    International Nuclear Information System (INIS)

    The cross sections of 28 reactions have been measured by the activation method since 1995 in CIAE. At the same time the cross sections of 40 reactions which we have measured since 1989 have been compiled and evaluated. A brief description of experimental measurement of activation cross sections is given. The data measured after 1995 by ourselves are listed in Table 4 and our evaluations for 40 reactions are listed in Table 5, respectively. A graphical intercomparison with available experimental data isi given in appendix. (author)

  10. Developing AMS measurement of $^{59}$Ni at CIAE

    OpenAIRE

    Ming, He; Wei, Wang; Xiangdong, Ruan; Chaoli, Li; Kejun, Dong; liang, Du; Bo, Xie Lin; Zhenyu, Li; Guowen, Zhen; Hao, Hu; J., Liu

    2013-01-01

    Accelerator mass spectrometry (AMS) measurement of $^{59}$Ni has been established at CIAE with the HI-13 tandem accelerator and the recently developed $\\Delta E$-Q3D detection system. $^{59}$Ni standard and commercial NiO samples were measured to check the performance of the $\\Delta E$-Q3D detection system on $^{59}$Ni isobar separation and suppression. An overall suppression factor of about 10$^{7}$ for the interfering isobar $^{59}$Co resulting in detection sensitivity as low as 3.8$\\times ...

  11. CIAE 600 kV ns pulse neutron generator

    International Nuclear Information System (INIS)

    The overall composition of CIAE 600 kV ns Pulse Neutron Generator (CPNG) are introduced, and its characteristic, main technological performance and application were also given. CPNG consists of high voltage power supply with highest output voltage 600 kV, direct current 15 mA, stability and ripple ≤0.1%, 2214 mm x 1604 mm x 1504 mm stainless steel high voltage electrode, built in head equipment uniform field accelerating tube, ns pulsed installation, turbomolecular vacuum pump system and drift pipes at 0 degree and 45 degree. Its characteristics are: (1) high current beam; (2) high current beam ns pulsed installation made use of low energy for chopper and high energy for buncher; (3) compactly laid out and simple in structure

  12. Research and development of in-core transducers at the CIAE

    International Nuclear Information System (INIS)

    In this paper, R and D of in-core transducers at the CIAE are briefly summarized. With the construction and commissioning of PWR nuclear power plant in China, fuel rod behaviour need to be studied carefully. As conventional transducers cannot meet the requirements of in-core applications, R and D of in-core transducers are developed. Since 1980's, several kinds of in-core transducers have been successfully fabricated and tested under the conditions simulating PWR. At present, in-pile tests of the transducers combining with the studies of individual behaviour of PWR fuel rod are being planned at the CIAE. (author). 11 refs, 12 figs, 4 tabs

  13. Recent progress in AMS measurement of 182Hf at the CIAE

    Institute of Scientific and Technical Information of China (English)

    LI Zhen-Yu; LI Heng; WU Shao-Yong; YUAN Jian; JIANG Shan; HE Ming; DONG Ke-Jun; HE Guo-Zhu; LI Chao-Li; HE Xian-Wen; ZHANG Wei; HU Hao; ZHENG Guo-Wen

    2012-01-01

    In order to improve the accuracy of accelerator mass spectrometry (AMS) measurement for 182Hf/180Hf,a series of measurements have been taken in the AMS laboratory at the China Institute of Atomic Energy (CIAE).The major ones include the instantaneous monitoring of 180HfF-5current,testing the stability of transmission,the alternate measurements of an unknown sample and standard,and the origin identification and minimization of background 182W.The experimental details and the improvement in the measurement accuracy,as well as some useful suggestions for better satisfying the requirements of certain practical applications,are presented in this paper.

  14. The measurement of {sup 129}I in ferromanganese crusts and aerosol samples with AMS at CIAE

    Energy Technology Data Exchange (ETDEWEB)

    Dong, Kejun, E-mail: dkj401@aliyun.com [China Institute of Atomic Energy, P.O. Box 275-50, Beijing 102413 (China); Jiang, Shan, E-mail: jiangs@ciae.ac.cn [China Institute of Atomic Energy, P.O. Box 275-50, Beijing 102413 (China); He, Ming; Lin, Min; Ouyang, Yinggen; Wu, Shaoyong [China Institute of Atomic Energy, P.O. Box 275-50, Beijing 102413 (China); Xie, Linbo; Liu, Guangshan; Ji, Lihong [College of Ocean and Earth Sciences, Xiamen University, Xiamen 361005 (China); Li, Qi; Wang, Shilian [CTBT Beijing National Data Centre and Radionuclide Laboratory, Beijing 100085 (China)

    2015-06-15

    The determination of long-lived nuclide {sup 129}I in terrestrial formations has many important applications. The AMS measurement method of {sup 129}I has been set up for many years at China Institute of Atomic Energy (CIAE). For further exploring the potential applications of {sup 129}I, samples of Deep Sea Ferromanganese Crusts (DSFC) and aerosol were analyzed by Accelerator Mass Spectrometry (AMS). The results show that {sup 129}I is not only a good tool for dating, but also an ideal nuclide for nuclear safety monitoring. The newest experimental progress and the main results are detailed in this presentation.

  15. Proceedings of the CIAE Pre-Conference (61st, Las Vegas, Nevada, November 4-6, 2012)

    Science.gov (United States)

    American Association for Adult and Continuing Education (NJ1), 2012

    2012-01-01

    The Commission on International Adult Education (CIAE) of the American Association for Adult and Continuing Education (AAACE) provides a forum for the discussion of international issues related to adult education in general, as well as adult education in various countries around the globe. The following purposes summarize the work of the…

  16. Measurement of 59Ni and 63Ni by accelerator mass spectrometry at CIAE

    Science.gov (United States)

    Wang, Xiaoming; He, Ming; Ruan, Xiangdong; Xu, Yongning; Shen, Hongtao; Du, Liang; Xiao, Caijin; Dong, Kejun; Jiang, Shan; Yang, Xuran; Lan, Xiaoxi; Wu, Shaoyong; Zhao, Qingzhang; Cai, Li; Pang, Fangfang

    2015-10-01

    The long lived isotopes 59Ni and 63Ni can be used in many areas such as radioactive waste management, neutron dosimetry, cosmic radiation study, and so on. Based on the large accelerator and a big Q3D magnetic spectrometer, the measurement method for 59Ni and 63Ni is under development at the AMS facility at China Institute of Atomic Energy (CIAE). By using the ΔE-Q3D technique with the Q3D magnetic spectrometer, the isobaric interferences were greatly reduced in the measurements of 59Ni and 63Ni. A four anode gas ionization chamber was then used to further identify isobars. With these techniques, the abundance sensitivities of 59Ni and 63Ni measurements are determined as 59Ni/Ni = 1 × 10-13 and 63Ni/Ni = 2 × 10-12, respectively.

  17. Symposium on CIAE 600 kV ns pulse neutron generator

    International Nuclear Information System (INIS)

    CIAE 600 kV ns Pulse Neutron Generator was built by China National Nuclear Corporation, which is an important facility mainly used for experimental researches of nuclear reactions induced by 14 MeV neutrons, experimental measurements of energy spectra of secondary neutrons and charged particles and macro-checking experiments of evaluated neutron database and dosimetry researches of neutrons and γ rays. It is the first home made one, but the fourth similar facility in the world. Six articles are included in this symposium. The articles details the general structure, radio frequency ion source, high current beam ns pulsed system, etc. The main technical problems resolved during development are discussed. And attentions and experiences in the generator adjustments are introduced

  18. Development of elemental and isotope analysis for nuclear safeguards in CIAE

    International Nuclear Information System (INIS)

    The 1990s saw significant non-proliferation related developments in the world, resulting in a new period of safeguards development. As a member of state of the IAEA, we attempted to do the supporting for IAEA's strengthem safeguards. CIAE Safeguards laboratory operates a diversity of NDA and DA equipments for nearly all analytical tasks within the scope of our experimental work and environmental monitoring. Gamma ray spectrometry multichannel analyzer, Neutron counting and physical property measurement etc have been applied for the control of nuclear materials processes. Elemental and isotope analysis have been made the significant progresses in the past ten years in CIAE safeguards laboratory. Inductively coupled plasma optical emission spectrometry (ICP-OES), energy dispersive X-ray fluorescence (XRF) are used for the determination of the impurities elements. The methods using quadrupole inductively coupled plasma mass spectrometry (Q-ICP-MS) and MC-ICP-MS for the measurement of the low-level concentration and isotopes of uranium, thorium and plutonium in environmental samples and nuclear materials have been set up, isotope dilution, and uncertainty discussed in the results. The anion resin, novel extraction chromatograph methods and argon-pressurized extraction column have been developed for the separation of trace radionuclides in the complexes system. In March 2001, a secondary ion mass spectrometry (SIMS) was installed and uranium isotopic ratio results of U-bearing particles have been studied. Thermal ionisation mass spectrometry (TIMS) is an internationally recognised analytical reference technique. Detailed study described for the determination of the isotopic composition and concentration of plutonium by the isotope dilution mass spectrometry (IDMS) using TIMS. The relative expanded uncertainty was 0.2% for the isotopic composition and 0.3% for the concentration of plutonium at 95% confidence level. (authors)

  19. The beam commissioning of BRIF and future cyclotron development at CIAE

    Science.gov (United States)

    Zhang, Tianjue; Yang, Jianjun

    2016-06-01

    As an upgrade project of the existing HI-13 tandem accelerator facility, the Beijing Radioactive Ion-beam Facility (BRIF) is being constructed in China Institute of Atomic Energy (CIAE). This project consists of an 100 MeV proton compact cyclotron, a two-stage ISOL system, a superconducting linac booster and various experimental terminals. The beam commissioning of the cyclotron was launched by the end of 2013 and on July 4, 2014 the first 100 MeV proton beam was received on a temporary target which was positioned at the outlet of the cyclotron. The beam current was stably maintained at above 25 μA for about 9 h on July 25, 2014 and the cyclotron is now ready for providing CW proton beam on target-source for RIB production. The beam current is expected to be increased to 200-500 μA in the coming years. The installation of the ISOL system is finished and the stable ion beam test shows it can reach a mass resolution better than 10,000. It is expected to generate dozens of RIB by 100 MeV proton beam. In addition, this paper also introduces the recent progress of the pre-study of an 800 MeV, 3-4 MW separate-sector proton cyclotron, which is aimed to provide high power proton beam for various applications, such as neutron and neutrino physics, proton radiography and nuclear data measurement and ADS system.

  20. Internal individual dose monitoring and estimation of dose equivalent from workers of the development and production of radioisotopes in CIAE

    International Nuclear Information System (INIS)

    The results of internal individual dose monitoring from workers of the development and production of radioisotopes in CIAE (1995-2000) are presented. The annual average committed effective dose is 1.8 x 10-2 - 8.0 x 10-1 mSv and the collective committed effective dose is 2.9 x 10-3 - 9.8 x 10-2 man·Sv in 1995-2000. The collective committed effective dose is 1.6 x 10-1 man·Sv and the annual average committed effective dose is 1.8 x 10-1 mSv for the 873 persons from 1995-2000

  1. Progress of Neutron Bubble Detectors in CIAE

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Neutron bubble detector is the only personal neutron dosimeter which has adequate neutronsensitivity to meet the implications of the ICRP 60 recommendations for neutron dosimetry. It canmonitor the wide range of neutron energy, for example 100 eV to 10 MeV And it becomes a significanttool for neutron dose monitoring at the environment of nuclear energy.

  2. Mini-Orange Spectrometer at CIAE

    CERN Document Server

    Zheng, Yun; Li, Guang-Sheng; Li, Cong-Bo; He, Chuang-Ye; Chen, Qi-Ming; Zhong, Jian; Zhou, Wen-Kui; Deng, Li-Tao; Zhu, Bao-Ji

    2016-01-01

    A Mini-Orange spectrometer used for in-beam measurements of internal conversion electrons, which consists of a Si(Li) detector and different sets of SmO$_5$ permanent magnets for filtering and transporting the conversion electrons to the Si(Li) detector, has been developed at China Institute of Atomic Energy. The working principle and configuration of the Mini-Orange spectrometer are described. The performance of the setup is illustrated by measured singles conversion electron spectra using the Mini-Orange spectrometer.

  3. Mini-orange spectrometer at CIAE

    Science.gov (United States)

    Zheng, Yun; Wu, Xiao-Guang; Li, Guang-Sheng; Li, Cong-Bo; He, Chuang-Ye; Chen, Qi-Ming; Zhong, Jian; Zhou, Wen-Kui; Deng, Li-Tao; Zhu, Bao-Ji

    2016-08-01

    A mini-orange spectrometer used for in-beam measurements of internal conversion electrons, consisting of a Si(Li) detector and different sets of SmO5 permanent magnets for filtering and transporting the conversion electrons to the Si(Li) detector, has been developed at the China Institute of Atomic Energy. The working principles and configuration of the mini-orange spectrometer are described. The performance of the setup is illustrated by measured singles conversion electron spectra using the mini-orange spectrometer. Supported by National Natural Science Foundation of China (11305269, 11375267, 11475072, 11405274, 11205068, 11175259)

  4. Status of the new nuclear energy systems study in CIAE

    International Nuclear Information System (INIS)

    The nuclear energy civil-application has been started in China. To meet the long-term sustainable primary energy supply it could be envisaged that the nuclear power systems will be developed in large scale. Following three key points must be satisfied by the future nuclear energy systems: - more safer nuclear energy systems than recent those should be developed to decrease the risk of core-melten and unforeseen release of radioactive materials; - long lived minor actinides and long lived fission products must be safely treated to assure a proper environment; - uranium resource should be sufficiently utilized. In order to meet above general requirements, the fast reactor technology development has been launched and the basic researches of Accelerator Driven Subcritical facility (ADS) system has been started in China. The activity of the construction of the China Experimental Fast Reactor and plan for next step, some calculation results on core physics study of ADS, some results on target physics and a proposed verification facility are briefed in the paper. (author)

  5. 236U measurement with accelerator mass spectrometry at CIAE

    International Nuclear Information System (INIS)

    236U is a long-lived radioactive isotope which is produced principally by thermal neutron capture on 235U. 236U may be potentially applied in geological research and nuclear safeguards. Accelerator mass spectrometry is presently the most sensitive technique for the measurement of 236U and a measurement method for long-lived heavy ion 236U has been developed. The set-up uses a dedicated injector and the newly proposed 208Pb16O2- molecular ions for the simulation of 236U ion transport. A sensitivity of lower than 10-10 has been achieved for the isotopic ratio 236U/238U in present work.

  6. Research and Development of GEM Foil at CIAE

    Institute of Scientific and Technical Information of China (English)

    LI; Xiao-mei; ZHOU; Jing; HU; Shou-yang; SHAN; Chao; JIAN; Si-yu; YE; Li; BAI; Xin-zhan; ZHOU; Shu-hua

    2012-01-01

    <正>China Institute of Atomic Energy has signed the "License Agreement for Manufacturing and Commercialisation of Gem Foils and Gem Based Products Licensee" with CERN, and got the technical assistance from CERN. The base material of GEM foil is ultrathin, non-adhesive copper on polyimide substrate, which can be purchased from CERN and other companies. The manufacture of GEM foil is

  7. Uranium Isotopic Ratio Analysis of U-Bearing Particulates By SIMS in CIAE

    International Nuclear Information System (INIS)

    In this paper measurement method of uranium isotope ratio of uranium-bearing particles in swipe samples was introduced; Swipe sample screening program was proposed on the basis of studying various destructive assay and non-destructive assays. Scanning electron microscope(SEM) equipped with an energy dispersive X-ray fluorescence(XRF) system was applied to located the deposited uranium-containning particles on the graphite support, particle's composition and size can be identified. Some isotope ratio results were compared with those of other bulk analytical methods; By measuring the same prepared sample, we got the U-particle isotopic ratio data similar to those from IAEA NWAL, indication that our operation parameters and experimental conditions are viable and can be used for measurement of U-particle isotope ratio from swipe samples

  8. Study on immobilization of spent ion exchange resins generated at CIAE

    International Nuclear Information System (INIS)

    At nuclear facilities the process for control system chemistry or the removal of radioactive containment in reactor primary coolants and /or cleanup of spent fuel pool, removal of boric acid and nuclear study centers have typically used organic ion exchange resin While their useful life ended, their ability of regeneration sharply depressed. Usually regeneration is not practiced. Due to considerable radioactive nuclei loading on it and in such a practice large amount of secondary liquid waste would be conducted to the waste treatment system. The used resin usually will be removed from the column and conveyed to shielded storage tank by compressed air system. Spent ion exchanger has been considered to be problematic wet solid waste. To avoid radiation dispersing into the environment, to make out an appropriate way for conditioning the waste is very important. According to contract with nation and Tsinghua university characterization of spent ion exchanger generated in our facilities has been finished at our lab. A direct cementation process has been set up and 1:1 scale demonstration has been fulfilled using formulation developed by Tsinghua University on the cementation process. Peak of temperature during hydration has been measured. Compressive strength and endure resistibility of the waste form for water and atmosphere have been tested. Results shown that performance of waste form can meet demand on national criteria. The process is easy to operate and its main advantages are described as following (1) the lay out of equipment is so compact that a shield from radiation for operation and maintenance is facilitated. (2) Type and shape of the resins involved in the experiment can completely represent that of reactors by now as well as in the future. (authors)

  9. A Conceptual Study of Hybrid System for Nuclear Energy Generation and Transmutation at CIAE

    International Nuclear Information System (INIS)

    Energy supply is a severe problem for developing country. Nuclear energy is just at its start in China. For developing nuclear energy three aspects must considered: 1. Nuclear waste handled properly: 2. Nuclear power station safety improved; 3. Natural Uranium resource utilization factor increased and new applicable resources expected. A research group for accelerator driven subcritical reactor in China Institute of Atomic Energy has been working for two years. Research results indicated subcritical reactor nuclear system driven by high intensity proton current accelerator can meet these requirements, that is 1. Subcritical reactor safety is accessible for the public 2. Some Short-lived. Low poison nuclear waste is removed from nuclear system, that is radioactive clean. 3. U-238 and Th-232 in the subcritical reactor can be converted into stationary nuclear fuel inventory to generate nuclear energy. The research results also indicated that the theoretical basis is right for accelerator driven subcritical reactor nuclear energy system, and has technological advantages for the further development of nuclear energy system which is different from conventional nuclear energy system, it's a technological innovation way for development of nuclear energy. During the early time of nuclear power exploitation and application in our country, it is worth to exploit this novel technological option.In this paper, discussion on the transmutation concept of high-level radioactive nuclide in nuclear waste is firstly conducted. And Then a brief description to the basic principle of ADS is given. The fission in the subcritical reactor with external neutron source is discussed. The relation ship of energy gain of the system, external neutron source with the subcritical reactor k is also discussed. (Author) 12 refs

  10. Primary result of 236U measurement with accelerator mass spectrometry at CIAE

    International Nuclear Information System (INIS)

    The rare isotope 236U has a half-life of 2.342(3) x 107 years, and is produced principally by thermal neutron capture on 235U. The isotopic atom ratio of 236U/238U depends on the integral thermal neutron flux received by the material of interest. 236U is potentially useful as a 'fingerprint' for indicating the presence of neutron-irradiated uranium usually originating from nuclear activity. By extracting negative molecular ion UO- from the uranium oxide target, simulating the 236U16O- beam transport with 238U16O- and 208Pb162 O- pilot molecular ion beam, transporting the 236U-containing ion beam with a high resolution injection magnet analyzer and electrostatic analyzer system, and finally identifying and detecting 236U with a time-of-flight detector (TOF), a method for AMS (Accelerator Mass Spectrometry) measurement of 236U was established on the HI-13 Accelerator AMS system at China Institute of Atomic Energy. (authors)

  11. International Scientific Technology Exchanges in 2012

    Institute of Scientific and Technical Information of China (English)

    LI; Lin

    2012-01-01

    <正>In 2012, CIAE sent 209 teams abroad for taking part in international meeting, technical visiting, further studying and training. CIAE received 412 foreign scholars from about 30 countries, and some reports were given by foreign scholars as follows:

  12. International Scientific Technology Exchanges in 2011

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    In 2012, CIAE sent 432 scholars abroad for taking part in international meeting, technical visiting, further studying and training. CIAE received more than 300 foreign scholars from about 30 countries, and some reports were given by foreign scholars as follows:

  13. International Scientific Technology Exchanges in 2013

    Institute of Scientific and Technical Information of China (English)

    LI; Tian; ZHANG; Xiao-qian

    2013-01-01

    In 2013,China Institute of Atomic Energy(CIAE)held a number of workshop,international conference and seminar.345 scholars from CIAE were sent abroad for technical visiting,further study and training and taking part in international conference.CIAE also received 360 foreign scholars from about 50 countries,and a large number of academic

  14. Influence Study on the Thermal Stability of N, N-Dimethylhydroxylamine in Nitric Acid Media

    Institute of Scientific and Technical Information of China (English)

    CAO; Zhi; BIAN; Xiao-yan; ZHENG; Wei-fang; YAN; Tai-hong

    2012-01-01

    <正>After years of research, CIAE (China Institute of Atomic Energy) has put forward the APOR (advance process based on organic reductants) which adopts N, N-dimethylhydroxylamine (DMHAN) as the new salt-free reductant. CIAE has carried out a lot of research work on the reaction kinetics for the DMHAN and Pu(Ⅳ), Np(Ⅴ/Ⅵ) and the reductive stripping kinetics for Pu(Ⅳ) and Np(Ⅵ). But CIAE

  15. International Scientific Exchanges in 2001

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    In 2001, China Institute of Atomic Energy (CIAE) signed 4 agreements 、 memorandums and 10 technical contracts with some institutes and companies of Russia, Cambodia, Korea and Belgium. CIAE sent 277 scientists, engineers and technical visitors jointed academic exchanges. Among of them, there were 91 person-times attended international conferences and symposiums, 28 person-times went abroad on the studied tour, 158 person-times worked or were trained through collaboration as well as contract implementations, etc.In 2001, CIAE held 5 international conferences and training courses in Beijing. CIAE received 497 foreign visitors from more than 30 counties and regions, they gave more than 400

  16. Brief introduction to 60 MW CARR

    Energy Technology Data Exchange (ETDEWEB)

    Yang Tonghua; Ye Chuntang [China Inst. of Atomic Energy, Beijing BJ (China)

    1998-10-01

    CARR, a 60 MW reactor will be constructed at China Institute of Atomic Energy (CIAE). The reactor type, its safety features, core lay-out, fuel assemblies, main parameters designed, main applications of are briefly described. (author)

  17. Self-shielding Electron Beam Installation for Sterilization

    Institute of Scientific and Technical Information of China (English)

    Linac; Laboratory

    2002-01-01

    China Institute of Atomic Energy (CIAE) has developed a self-shielding electron beam installationfor sterilization as handling letters with anthrax germ or spores which has the least volume and the least

  18. Advancement of German Neutron Spectrometers Relocation Project in 2008

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>Neutron scattering technique is going on in Neutron Scattering Laboratory (NSL) of China Institute of Atomic Energy (CIAE) based on China Advanced Research Reactor (CARR), which will be hopefully

  19. Planning for the decommissioning of a heavy water research reactor

    International Nuclear Information System (INIS)

    The Heavy Water Research Reactor (HWRR) was constructed and put into operation in 1958 at the China Institute of Atomic Energy (CIAE), located in the suburbs of Beijing. It was the first nuclear reactor in China. The HWRR is a 10 MW multipurpose research reactor and has been operated for 48 years. Because of its long operating history and aged equipment, it is scheduled to be finally shut down by the end of 2007. It has been decided by CIAE to implement a strategy of immediate dismantling after final shutdown. The paper describes the preparation work for the development of the HWRR decommissioning plan at CIAE. The establishment and organization of the project and the problems encountered are described. Progress and problems are addressed. The paper also discusses the measures needed for the successful planning of decommissioning. (author)

  20. Entropy Evolution Characteristics and Relationship With Hybrid Ratios for UHNTF

    Institute of Scientific and Technical Information of China (English)

    FANG; Jin-qing; LI; Yong

    2012-01-01

    <正>Based on the Unifying Hybrid Network theory frameworks (UHNTF) proposed by CIAE network group, Boltzmann-Gibbs entropy (BGS) and Tsallis entropy evolution characteristics of complex networks with different hybrid ratios and their relations are revealed by theoretical and numerical research.

  1. Structure of Self-shielding Electron Beam Installation for Sterilization

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    In order to prevent terrorist using letters with anthrax germ or spores to postal route and disturbsociety, and defend the people’s life-safety China Institute of Atomic Energy (CIAE) has developed aself-shielding electron beam installation for sterilization (SEBIS).

  2. Refurbishment Status of Light Ⅱ-A Pulsed Power Generator

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The Light Ⅱ-A pulsed power generator, formerly used to pump KrF laser, was updated around the year 2000 from the original Light Ⅱ, a pulsed power generator built in 1980s at CIAE. This machine was

  3. 10 MeV Medical Cyclotron Prototype Beam Commissioning

    Institute of Scientific and Technical Information of China (English)

    GUAN; Feng-ping; GE; Tao; YIN; Zhi-guo; SONG; Guo-fang; ZHANG; Tian-jue; JI; Bin; LI; Peng-zhan; CAO; Lei; HOU; Shi-gang; LIU; Geng-shou; WANG; Feng; LEI; Yu; WU; Long-cheng; WEN; Li-peng; LI; Zhen-guo; CUI; Tao; JIA; Xian-lu; YAO; Hong-juan; PAN; Gao-feng; ZHANG; Su-ping; CAI; Hong-ru; XIE; Huai-dong

    2012-01-01

    <正>A 10 MeV medical cyclotron prototype for the production of short-lived isotopes has been developed independently at CIAE with a time span of 2 years. On the inner target, 8 hours stability test has been finished. The extraction beam is 10 MeV with a beam intensity of 100 μA.

  4. Progress Report of Small Angle Neutron Scattering at CARR

    Institute of Scientific and Technical Information of China (English)

    ZHANG; Li; LI; Tian-fu; WEI; Guo-hai; WANG; Yu; WANG; Hong-li; LIU; Yun-tao; CHEN; Dong-feng

    2012-01-01

    <正>Significant progress towards the commissioning of the IOCCAS-CIAE SANS facility at China Advanced Research Reactor (CARR) has been made. The project of this SANS spectrometer belongs to "building up the center for neutron scattering". The installation work was already done in last two years. In this year, the instrument adjustment and calibration were done with the test CARR. First, the

  5. Radioactive Waste Treatment and Disposal——Application Process for Immobilization of Spent Organic Ion Exchanger

    Institute of Scientific and Technical Information of China (English)

    LINMei-qiong; GANXue-ying; BAOLiang-jin; CHENHui

    2003-01-01

    Cementation process used ASC matrix is developed by CIAE. The primary objective of the project is to provide 200 L drum scale process parameter and make an improved formulation of waste form.Scientific researchers of Tsinghua take the responsibility for improving on formulation in final waste form and ensuring quality can meet requirement of GB 14569.1-93.

  6. Technique of chemical cleaning for removing corrosion products in nuclear reactor (PWR)

    International Nuclear Information System (INIS)

    The study of chemical cleaning technique for removing corrosion products in PWR type plant and power reactor have been carried in China Institute of Atomic Energy (CIAE), Beijing. The report summarizes the in results of screening test and qualification test of chemical cleaning technique, and the results of chemical cleaning to remove corrosion products (Fe304) in primary side of PWR type power reactor which chemical cleaning process has been carried by CIAE. The chemical cleaning agent (EDTA + assistant agent + inhibitor ) is effective for removing magnetite (Fe304 ≤ 17.5g/l).The process of chemical cleaning includes cleaning, rinse, passivation. The corrosion rate of materials is acceptable. The chemical cleaning technique is effective and safe for PWR type reactor. (author)

  7. Calibration of a compact magnetic proton recoil neutron spectrometer

    Science.gov (United States)

    Zhang, Jianfu; Ouyang, Xiaoping; Zhang, Xianpeng; Ruan, Jinlu; Zhang, Guoguang; Zhang, Xiaodong; Qiu, Suizheng; Chen, Liang; Liu, Jinliang; Song, Jiwen; Liu, Linyue; Yang, Shaohua

    2016-04-01

    Magnetic proton recoil (MPR) neutron spectrometer is considered as a powerful instrument to measure deuterium-tritium (DT) neutron spectrum, as it is currently used in inertial confinement fusion facilities and large Tokamak devices. The energy resolution (ER) and neutron detection efficiency (NDE) are the two most important parameters to characterize a neutron spectrometer. In this work, the ER calibration for the MPR spectrometer was performed by using the HI-13 tandem accelerator at China Institute of Atomic Energy (CIAE), and the NDE calibration was performed by using the neutron generator at CIAE. The specific calibration techniques used in this work and the associated accuracies were discussed in details in this paper. The calibration results were presented along with Monte Carlo simulation results.

  8. Monte Carlo Study of a 137Cs calibration field of the China institute of atomic energy

    CERN Document Server

    Gao, Fei

    2015-01-01

    The MCNP code was used to study the characteristics of gamma radiation field with collimated beam geometry. A close-to-reality simulation model of the facility was used for calculation air-kerma along the whole range of source-detector-distance (SDD) along the central beam and air-kerma off-axis beam profiles at two different source-detector-distance (SDD). The simulation results were tested by the measured results which were acquired in the Radiation Metrology Center of CIAE. Other characteristics such as the individual contributions of photons scattered in collimator, floor, walls, mobile platform and other parts of the irradiation halls to the total air kerma rate on the beam axis were calculated for the purpose of future improvement of metrological parameters in CIAE. Finally, factors which influence the simulation results were investigated, including e.g., detector volume effects or source density effects.

  9. Products of Security Inspecting Have Been Sold to Tanzania

    Institute of Scientific and Technical Information of China (English)

    LI; Yong; WANG; Qiang; GAO; Qi; TIAN; Li-jun; YANG; Lu; ZHENG; Yu-lai; GUO; Feng-mei

    2013-01-01

    Products of security inspecting of China Institute of Atomic Energy(CIAE)have been applied to many major sports events,such as Olympics hold at Beijing in 2008 and World Expo hold at Shanghai in2010,and other important places such as Great Hall and National Theatre.Passage-type inspection system of radioactive materials(RMS),portable radionuclide spectrometer(PRIS),and walk-through metal and radioactive materials detector(MRMD)have been sold to the user of Tanzania.

  10. Measurement of the Fucosylated Sugar Chains of Serum α_1-Antitrypsin : The Relationship between Reactivity with Lens Culinaris Agglutinin and HPLC Analysis of the Pyridylaminated Sugar Chains

    OpenAIRE

    Saitoh, Atsushi; Aoyagi, Yutaka; Mori, Shigeki; Suda, Takeshi; Suzuki, Yasufumi; Sekine, Chuichi; Asakura, Hitoshi

    1997-01-01

    Twelve samples of α_1-anlitrypsin (AAT) were purified from six patients with hepatocellular carcinoma, one with pancreatic cancer and five healthy individuals, and subjected to the measurement of the fucosylated sugar chain. We compared different results from crossed immunoaffinoelectrophoresis (CIAE) with Lens culinaris agglutinin (LCA) and by the carbohydrate analysis of high-performance liquid chromatography (HPLC) with the pylidylaminated (PA・) oligosaccharides obtained from each AAT. A s...

  11. 中国原子能科学研究院的加速器质谱系统及其应用

    Institute of Scientific and Technical Information of China (English)

    何明; 姜山; 武绍勇; 董克君; 管永精; 李世红

    2004-01-01

    The accelerator mass spectrometry system(AMS) in China Institute of Atomic Energy(CIAE) has been improved especially for the ion source, some new measurement methods including 41Ca measurement, PX-AMS method and GF-TOF detector are developed, the applications of the AMS system including nuclear physics science, environmental science, geoscience, life science and materials science have been carried out, a brief describe of all these work is discussed in this paper.

  12. In-pile test of Qinshan PWR fuel bundle

    International Nuclear Information System (INIS)

    In-pile test of Qinshan Nuclear Power Plant PWR fuel bundle has been conducted in HWRR HTHP Test loop at CIAE. The test fuel bundle was irradiated to an average burnup of 25000 Mwd/tU. The authors describe the structure of (3 x 3-2) test fuel bundle, structure of irradiation rig, fuel fabrication, irradiation conditions, power and fuel burnup. Some comments on the in-pile performance for fuel bundle, fuel rod and irradiation rig were made

  13. Progress of Nuclear Data Measurement in China during 2013

    International Nuclear Information System (INIS)

    The China nuclear data activities consists of nuclear data measurement and related measurement methods development, data evaluation and model study, data library establishment and library management, nuclear data benchmark and validation. The main activities are being carried out at China Nuclear Data Center (CNDC), China Institute of Atomic Energy (CIAE) and China Nuclear Data Coordination Network (CNDCN). More than 10 institutions and universities are involved in CNDCN. The facilities used for the nuclear data measurements and studies include the HI-13 tandem accelerator, 600 kV-Cockcroft-Walton accelerator, 5SDH-2 2x1.7 MV tandem accelerator and the China Advanced Research Reactor (CARR) at CIAE, The 4.5-MV Van de Graaff accelerator at Peking University and 300 kV -Cockcroft-Walton accelerator at Lanzhou university. This document presents the recent Progress of Nuclear Data Measurement in China: - the fission yields of 235U at 3 MeV neutrons measured at CIAE; - the nuclear data benchmark system improvement at CIAE. With the new nuclear data benchmark system, the integral measurements were carried out for Be, Ga, natural iron and liquid Pb-Bi alloy. - The measurements of the 57Fe(n,α)54Cr and 63Cu(n,α)60Co reactions at neutron energies of 5.0, 5.5, 6.0 and 6.5 MeV at Peking University. Finally, the document describes the new facilities for Nuclear Data Measurement: the Back-n white neutron source of the China Spallation Neutron Source (CSNS), the neutron facility of Shanghai Institute of Applied Physics (SINAP-NF), and the multipurpose Cooling Storage Ring system, a new accelerator project planned at the Heavy Ion Research Facility in Lanzhou (HIRFL-CRS)

  14. Measurement of Neutron Transmission for Tungsten With 2.8 MeV Neutrons

    Institute of Scientific and Technical Information of China (English)

    REN; Jie; RUAN; Xi-chao; BAO; Jie; NIE; Yang-bo; ZHOU; Zu-ying

    2012-01-01

    <正>The neutron transmission for different thickness of tungsten plates for 2.8 MeV neutrons was measured with TOF technique using the d-D reaction neutron source at the 600 kV Cococroft-Walton accelerator at CIAE. The sensitivity for distinguishing the thickness of the tungsten plate was determined with this method. The tungsten plate was put at the beam direction and 1.7 m from the neutron source, and

  15. FDD-1 System On-line Monitoring Fuel Rod Failure of Nuclear Power Plant

    Institute of Scientific and Technical Information of China (English)

    CHENPeng; ZHANGYing-chao; JISong-tao; GAOYong-guang; YINZhen-guo; HANChuan-bin

    2003-01-01

    The FDD-1 system developed by CIAE for on-line monitoring fuel rod failure of nuclear power plant consists of γ-ray detector, γ-ray spectrum analyzer, computer, and an analysis code for evaluating the status of fuel rod failure. It would be determined that the fuel rod failure occurs when a large amount of γ activity increases in the primary system measured by γ-ray detector near the CVCS.

  16. Annual Report of Radioactive Waste Facilities Operation in 2013

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; LIU; Fu-guo

    2013-01-01

    301,a section of Department of Radiochemistry,which manages 15 facilities and undertakes the administrative tasks of radioactive waste,is the important guarantee of scientific research production and safety in CIAE.1 The safe operation of the radioactive waste management facilities In 2013,in order to ensure the operation safety,we formulated the inspection regulations,which included regular operation inspection,week safety inspection from the leaders of the section and

  17. Performance test of large BaF2 detector

    International Nuclear Information System (INIS)

    The γ total absorption facility (GTAF) was being built in China Institute of Atomic Energy (CIAE). It was composed of 40 BaF2 detector modules. The performance of every single module, such as detector construction, choosing of crystal packaging condition, energy resolution, time resolution, and long time stability were tested. From the energy resolution and time resolution test, it shows that the detector modules are good for using in neutron capture cross section measurement. (authors)

  18. Wavelength calculation of highly stripped ions S10+→S13+, Br23+, Br24+, Ge20+, Ge21+

    International Nuclear Information System (INIS)

    Wavelengths of highly stripped ions S10+ →S13+ , Br23+ , Br24+ , Ge20+ , Ge21+ are calculated by means of GRASP code. The calculations are performed based on multiconfiguration Dirac-Fock technique. Corrections to the energy levels due to the retarded Coulomb interaction (Breit interaction) and the polarization of the vacuum by the nuclear distribution and electron self-energy are included in a perturbation approximation. Comparisons with the new experimental data by CIAE group are presented

  19. Investigation of fast chemistry separation for 95Y

    International Nuclear Information System (INIS)

    The separation condition of strontium from fission products using SISAK system and yttrium from Sr-Y mixture was studied. The separation process was optimized. The method that separates Sr-Y after separation of strontium from fission products was selected, which was based on the half-life difference between 94Sr and 95Sr. Combined the fast chemistry separation and decay characteristic, 95Y was separated successfully in the mini-reactor in CIAE. The recommended technological process was given. (authors)

  20. Electromagnetic isotope separation at the China Institute of Atomic Energy

    Energy Technology Data Exchange (ETDEWEB)

    Li Gongpan; Lin Zhizhou; Xiang Xuyang; Deng Jingting (China Inst. of Atomic Energy, Beijing, BJ (China))

    1992-08-01

    Electromagnetic isotope separation at the China Institute of Atomic Energy (CIAE) is described. Calutron, Nier-Bernas and Freeman ion sources were constructed for ion implantation systems. It was found that some enriched isotope samples were contaminated more by lighter than by heavier neighbors. This phenomenon may be explained if the sputtered particles consist of a considerable percentage of ions. A computer inspection system for recording and processing operation data has been designed. (orig.).

  1. Radio frequency ion source

    CERN Document Server

    Shen Guan Ren; Gao Fu; LiuNaiYi

    2001-01-01

    The study on Radio Frequency Ion Source is mainly introduced, which is used for CIAE 600kV ns Pulse Neutron Generator; and obtained result is also presented. The RF ion source consists of a diameter phi 25 mm, length 200 mm, coefficient of expansion =3.5 mA, beam current on target >=1.5 mA, beam spot =100 h.

  2. Design of a compact, permanent magnet electron cyclotron resonance ion source for proton and H2+ beam production

    International Nuclear Information System (INIS)

    A 2.45 GHz microwave ion source was developed at China Institute of Atomic Energy (CIAE) for proton beam production of over 60 mA [B.-Q. Cui, Y.-W. Bao, L.-Q. Li, W.-S. Jiang, and R.-W. Wang, Proceedings of the High Current Electron Cyclotron Resonance (ECR) Ion Source for Proton Accelerator, APAC-2001, 2001 (unpublished)]. For various proton beam applications, another 2.45 GHz microwave ion source with a compact structure is designed and will be built at CIAE as well for high current proton beam production. It is also considered to be used for the test of H2+ beam, which could be injected into the central region model cyclotron at CIAE, and accelerated to 5 MeV before extraction by stripping. The required ECR magnetic field is supplied by all the permanent magnets rather than electrical solenoids and six poles. The magnetic field distribution provided by this permanent magnets configuration is a large and uniformly volume of ECR zone, with central magnetic field of a magnitude of ∼875 Gs[T. Taylor and J. S. C. Wills, Nucl. Instrum. Methods Phys. Res. A 309, 37 (1991)]. The field adjustment at the extraction end can be implemented by moving the position of the magnet blocks. The results of plasma, coupling with 2.45 GHz microwave in the ECR zone inside the ion source are simulated by particle-in-cell code to optimize the density by adjusting the magnetic field distribution. The design configuration of the ion source will be summarized in the paper.

  3. Angular Distribution of the 12C(6He, 7Li)11B Reaction

    Institute of Scientific and Technical Information of China (English)

    LI Er-Tao; LI Zhi-Hong; LI Yun-Ju; YAN Sheng-Quan; BAI Xi-Xiang; GUO Bing; SU Jun; WANG You-Bao; WANG Bao-Xiang; LIAN Gang; ZENG Sheng; FANG Xiao; ZHAO Wei-Juan; LIU Wei-Ping

    2009-01-01

    Angular distribution of the 12C(6He, 7Li)11B transfer reaction is measured with a secondary 6He beam of 36.4 Me V for the first time. The experimental angular distribution is well reproduced by the distorted-wave Born approxima-tion (DWBA) calculation. The success of the present experiment shows that it is feasible to measure one-nucleon transfer reaction on a light nucleus target with the secondary beam facility of the HI-13 tandem accelerator at China Institute of Atomic Energy (CIAE), Beifing.

  4. Prácticas pedagógicas y competencias ciudadanas: El caso del docente de historia en Chile

    OpenAIRE

    Muñoz Labraña, Carlos; Martínez Rodríguez, Rosendo

    2015-01-01

    En el presente artículo exponemos los resultados obtenidos sobre las prácticas pedagógicas y las competencias ciudadanas en una investigación financiada por el Centro de Investigación Avanzada en Educación (CIAE). En él analizamos algunas de las estructuras comunicativas presentes en la intervención didáctica del docente de Historia, Geografía y Ciencias Sociales de quinto a octavo año de Educación Básica en la ciudad de Concepción (Chile), desde donde se atiende la forma como estas interfier...

  5. Measurement of Secondary Neutron Emission Double-Differential Cross Section for Deuteron Induced by 8.22 MeV Neutrons

    Institute of Scientific and Technical Information of China (English)

    LIN; Meng-na; RUAN; Xi-chao; HUANG; Han-xiong; REN; Jie; LI; Yong-ming; LI; Xia; NIE; Yang-bo; ZHANG; Qi-wei; HE; Guo-zhu; ZHOU; Zu-ying

    2012-01-01

    <正>This experiment is performed to measure the time-of-flight spectra of secondary neutrons for deuteron induced by 8.22 MeV neutrons in the range of 15o-155o for CD2 and C samples, and 15o -65o for a polyethylene sample, by using the multi-detector fast neutron TOF spectrometer at the China institute of Atomic Energy (CIAE). The D(d, n)3He reaction source was used. The influence of the C in the CD2

  6. The performance and application of laser-induced photoacoustic spectrometer

    International Nuclear Information System (INIS)

    Laser-induced photoacoustic spectrometer (LIPAS) is a key instrument can be used in the investigation of radionuclides migration behaviors due to its higher sensitivity for the detection and identification of radionuclides speciation in aqueous solutions. The speciation of radionuclides such as oxidation states and complexation may be determined directly by using this specific non-contact and nondestructive analytical technique, and the sensitivity of LIPAS surpasses that of conventional absorption spectroscopy by one to two orders of magnitude. In the present work, LIPAS system was established at China Institute of Atomic Energy (CIAE), and the principle, performance and preliminary application of LIPAS are also be presented. (authors)

  7. Excitation functions of reactions from d + Ti, d + Mo, p + Ti and p + Mo

    International Nuclear Information System (INIS)

    The excitation functions for the products of 48V, from P + Ti and d + Ti and of 95Tcm,g, 96Tcg and 99Mo from P + Mo and d + Mo were studied. The excitation functions were measured by the conventional stacked foil method. The experiments were carried out at the HI-13 tandem accelerator of CIAE in the energy range from threshold to 22 Mev. The excitation functions leading to the formation of 48V, 95Tcm,g, 96Tcg and 99Mo are presented

  8. State and prospects of thermal neutron scattering work in China

    International Nuclear Information System (INIS)

    Thermal neutron scattering is an important branch of applied nuclear technology. The only thermal neutron scattering laboratory in China has been established, at CIAE, where the experimental facilities are available to the scientists from all over the country. During the past years thermal neutron scattering technology in this laboratory has been applied to some fields, thus several research orientations being formed. Interesting results in both basic and applied sciences have been obtained. If continuing supports are offered, more creative works will be done in the near future

  9. Development, Characterization and Testing of Materials of Relevance to Nuclear Energy Sector Using Neutron Beams in China

    International Nuclear Information System (INIS)

    A 60 MW research reactor, so called China Advanced Research Reactor (CARR,) was built in CIAE, neutron scattering and neutron imaging are one of the main research and application fields based on it. With the support of members in the CRP initiated by IAEA five instruments related to applications on materials of relevance to nuclear energy sector, have been designed/improved and constructed. Since August 21st, 2012 instruments started to do commissioning with neutrons and some scientific research related to nuclear materials were also carried out at CARR and abroad. (author)

  10. Assessment of a general methodology for the analysis of natural circulation stability with water at supercritical pressure

    International Nuclear Information System (INIS)

    To advance nuclear energy to meet future energy needs, the concept of Super Critical Water-Cooled Reactor (SCWR) as part or Generation IV (Gen IV) reactors was introduced with plans to deploy by 2030. Supercritical water-cooled reactors pose new challenges in stability and natural circulation phenomena at supercritical pressures because of the strong variability of thermodynamic and thermo-physical properties. ln this research, included in the frame work of the International Atomic Energy Agency (lAEA) fellowship and Coordinated Research Project (CRP) on Heat transfer Behavior and Thermo hydraulics Codes Testing for SCWRs, the natural circulation H2O experimental data at supercritical pressures of 25 MPa obtained at the China Institute of Atomic Energy (CIAE) of China, was used to evaluate the predictions of different system codes: RELAP5/MOD3.3, STAR-CCM+ as well as three (3) different and independent developed in-house codes (Ishii-sup loop, NCLoopTran and NCLoopLine). Stability analyses of an idealized loop (loop equivalent to CIAE natural circulation loop) of uniform diameter equivalent to the CIAE natural circulation loop at 25 MPa was performed using RELAP5 and an in-house code (Ishii-sup Loop). It was found for both RELAP and Ishii-sup Loop that, when heat structures are accounted for in models equipped with heat transfer and friction correlations for 'normal' fluids, the comparison with experimental data is not completely satisfactory because the observed experimental oscillations were delayed in simulation. It has also been found that the stability margin was slightly earlier than the peak of the flow rate-power curve at a given inlet enthalpy. Results from STAR-CCM+ was also compared with results obtained with RELAP5 and the in-house code of NCLoop. Even though STAR-CCM+ predicted a lower flow rate than the in-house codes, all codes exhibited the ability to predict the instability and results from all codes compared favorably. Stability analyses

  11. Advances in theoretical models of network science

    Institute of Scientific and Technical Information of China (English)

    FANG Jin-qing; BI Qiao; LI Yong

    2007-01-01

    In this review article, we will summarize the main advances in network science investigated by the CIAE Group of Complex Network in this field. Several theoretical models of network science were proposed and their topological and dynamical properties are reviewed and compared with the other models. Our models mainly include a harmonious unifying hybrid preferential model, a large unifying hybrid network model, a quantum interference network, a hexagonal nanowire network, and a small-world network with the same degree. The models above reveal some new phenomena and findings, which are useful for deeply understanding and investigating complex networks and their applications.

  12. The physics design of magnet in 14 MeV cyclotron

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The 14 MeV, 400 μA compact cyclotron is under construction at China Institute of Atomic Energy (CIAE). The design of main magnet and the result of beam dynamics in the cyclotron will be described in this paper, including the choice of main parameters of magnet, the method of shimming isochronous field in the compact cyclotron and optimization of the magnetic field in central region. The beam will be accelerated to 14.6 MeV by optimizing the magnet structure.

  13. Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

    International Nuclear Information System (INIS)

    This report is a compilation of the information submitted by AECL, CIAE, JAERI, ORNL and Siemens in response to a need identified at the 'Workshop on R and D Needs' at the IGORR-3 meeting. The survey compiled information on the national standards applied to the Safety Quality Assurance (SQA) programs undertaken by the participants. Information was assembled for the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods used to verify and validate the codes and libraries. Although the survey was not comprehensive, it provides a basis for exchanging information of common interest to the research reactor community

  14. MFM Automatic Control System Development for CYCIAE-100

    Institute of Scientific and Technical Information of China (English)

    CAO; Lei; YIN; Zhi-guo; LV; Yin-long; ZHONG; Jun-qing

    2012-01-01

    <正>In order to do the magnetic field measurement (MFM) work for CYCIAE-100, a set of MFM automatic facility has been developed by the cyclotron team at CIAE. 1 Design of project The MFM facility for CYCIAE-100 adopts the method of circular and radial motion to complete the measurement. In circular direction, an open loop control is adopted at hardware level. A kind of arithmetic is compensated to form a virtual closed loop control based on the position signal by angle encoder

  15. Simulating transients in the subcritical reactor by using a sealed-tube neutron generator

    International Nuclear Information System (INIS)

    Research on transients is one of the main focuses in the field of accelerator driven subcritical reactor (ADSR). But inducing the transients by accelerator is inconvenient and costly. Simulating transients by sealed tube neutron generator, through improving the driver of Penning ion source and modulating trigger signals of pulsed neutron, is a fast, accurate, reliable and low-cost method. This method has been used in simulating transients on the physics test platform of ADSR in China Institute of Atomic Energy (CIAE). And this method also can be applied in PGNAA. (author)

  16. Measurement of the cross sections for the 175Lu(n,2n)174m,gLu reaction

    International Nuclear Information System (INIS)

    The 175Lu(n,2n)174m,gLu reaction is an important indicator. There are 10 sets of measured data since 1960 (total 58 experimental values). Most of the data are finished at 14 MeV with 20%∼30% discrepancy. So the authors measured the cross section by activation method in neutron energies of 14 MeV and 10∼12 MeV. The measurement is carried out at the Cockcroft-Walton and HI-13 Tandem accelerator of CIAE

  17. Study on coincidence measurement for 56Fe(n, χnγ) reaction cross section

    International Nuclear Information System (INIS)

    When measuring (n, χnγ) partial γ-ray cross section of heavy fissionable nuclei, the technique of coincidence measurement was applied to depress Compton platform and background of energy spectrum. Five energy points of 56Fe(n, χnγ) cross sections were measured directly by two Clover detectors on 600 kV Cockcroff-Walton accelerator in CIAE, and then the offline data analysis at 1238.3 keV was performed by using the coincidence technique. The result is approximately the same as direct measurement result and the availability of the technique of coincidence measurement is proved. (authors)

  18. Study on a new calibration methods of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    A new calibration technique, which is the Monte Carlo modeling technique, of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning, is presented. A series of assay for some stainless steel pipes and tanks in some nuclear facilities/laboratories of CIAE are taken on site with the in-situ HPGe γ spectrometer. At the same time, some examples are taken and analyzed in laboratories. The relative bias/variation between the values of activity measured by in-situ HPGe γ spectrometers on site and that analyzed in laboratory is less than ±45.0%. (authors)

  19. The China Institute of Atomic Energy

    International Nuclear Information System (INIS)

    The China Institute of Atomic Energy (CIAE), established in 1950, carries out multidisciplinary research in nuclear science, technology and engineering. It has three research reactors and ten low energy accelerators. The focus of its nuclear energy related R and D is on reactor engineering and technology. In the area of nuclear techniques for applications, R and D is carried out on accelerators, isotope production, nuclear electronics and utilization of radioisotopes and radiation. There is also a strong programme in basic nuclear physics and radiochemistry. New major facilities under construction in CIAE include China Advanced Research Reactor (flux 8x1014n/cm2/sec) and China Experimental Fast Reactor. China has been successfully using the products of its R and D for a variety of applications in medicine, industry, materials science etc. A dynamic research programme is tuned to attract young talent to CIEA and there is good collaboration with the Beijing University. CIEA has been an active participant of RCA programmes of the IAEA and has been a resource for many developing countries. The management expects the Institute to be a leading multidisciplinary institute in the field of nuclear science, technology and engineering. (author)

  20. Development of a low-level RF control system for PET cyclotron CYCIAE-14

    Energy Technology Data Exchange (ETDEWEB)

    Li, Pengzhan, E-mail: lipengzhan@ciae.ac.cn; Yin, Zhiguo; Ji, Bin; Zhang, Tianjue; Zhao, Zhenlu

    2014-01-21

    The project of a 14 MeV PET cyclotron aiming at medical diagnosis and treatment was proposed and started at CIAE in 2010. The low-level RF system is designed to stabilize acceleration voltage and control the resonance of the cavity. Based on the experience of the existing CRM Cyclotron in CIAE, a new start-up sequence is developed and tested. The frequency sweeping is used to activate the RF system. Before the tuner is put into use, a new state called “DDS tuning” is applied to trace the resonance frequency to the designed value. This new option state helps to cover the tuning range, if a large frequency variation occurs because of a thermal cavity deformation. The logic control unit detects the spark, reflection, Pulse/CW state and the frequency of the RF source to perform all kinds of protection and state operations. The test bench and on-line test are carried out to verify the initial design. -- Highlights: • The low-level RF system is designed and verified for PET cyclotron CYCIAE-14. • The frequency sweeping is used to activate the RF system. • A new state called “DDS tuning” is applied to trace the resonance frequency. • This new option state helps to cover the tuning range. • Protection module allows a quick restart after an alarm and improves cyclotron's efficiency.

  1. Development of a low-level RF control system for PET cyclotron CYCIAE-14

    Science.gov (United States)

    Li, Pengzhan; Yin, Zhiguo; Ji, Bin; Zhang, Tianjue; Zhao, Zhenlu

    2014-01-01

    The project of a 14 MeV PET cyclotron aiming at medical diagnosis and treatment was proposed and started at CIAE in 2010. The low-level RF system is designed to stabilize acceleration voltage and control the resonance of the cavity. Based on the experience of the existing CRM Cyclotron in CIAE, a new start-up sequence is developed and tested. The frequency sweeping is used to activate the RF system. Before the tuner is put into use, a new state called "DDS tuning" is applied to trace the resonance frequency to the designed value. This new option state helps to cover the tuning range, if a large frequency variation occurs because of a thermal cavity deformation. The logic control unit detects the spark, reflection, Pulse/CW state and the frequency of the RF source to perform all kinds of protection and state operations. The test bench and on-line test are carried out to verify the initial design.

  2. Determination of cross sections of 60Ni(n,2n)59Ni induced by 14 MeV neutrons with accelerator mass spectrometry

    Science.gov (United States)

    He, Ming; Xu, Yongning; Guan, Yongjing; Shen, Hongtao; Du, Liang; Hongtao, Chen; Dong, Kejun; Jiang, Shan; Yang, Xuran; Wang, Xiaoming; Ruan, Xiang dong; Liu, Jiancheng; Wu, Shaoyong; Zhao, Qingzhang; Cai, Li; Pang, Fangfang

    2015-10-01

    The cross section of the 60Ni(n,2n)59Ni induced by neutron with energy around 14 MeV is important for a fusion environment. However, the published values are strongly discordant. By taking advantage of the high sensitivity of 59Ni measurement at China Institute of Atomic Energy (CIAE), determination of the cross section has been carried out. A natural Nickel foil was irradiated by neutrons produce by a T(D,n)α neutron generator. 57Co and 58Co which produced in the Nickel foil were chosen for the neutron fluence determination. Then the ratio of 59Ni/60Ni for the irradiated sample was determined via accelerator mass spectrometry (AMS) utilizing a 13MV tandem accelerator and a Q3D magnet spectrometry at CIAE. As a result, the cross section of 60Ni(n,2n)59Ni for the incident neutron energy of (14.60 ± 0.40) MeV was determined to be (426 ± 53) mb.

  3. Measurement of secondary neutron emission double-differential cross sections for 9Be induced by 21.65 ± 0.07 MeV neutrons

    Science.gov (United States)

    Lan, Changlin; Ruan, Xichao; Chen, Guochang; Nie, Yangbo; Huang, Hanxiong; Bao, Jie; Zhou, Zuying; Tang, Hongqing; Kong, Xiangzhong; Peng, Meng

    2016-05-01

    The neutron emission double-differential cross sections (DDX) of 9Be was measured at an incident neutron energy of 21.65 MeV, using the multi-detector fast neutron time-of-flight (TOF) spectrometer on HI-13 Tandem Accelerator at the China Institute of Atomic Energy (CIAE). The data were deduced by comparing the measured TOF spectra with the calculated ones using a realistic Monte-Carlo simulation. The DDX were normalized to n-p scattering cross sections which are a neutron scattering standard. The results of the elastic scattering angular distributions (DX) and the secondary neutron emission DDX at 25 different angles from 15 deg to 145 deg were presented. Meanwhile, a theoretical model based on the unified Hauser-Feshbach and exciton model for light nuclei was used to describe the double-differential cross sections of n+9Be, and the theoretical calculation results were compared with the measured cross sections.

  4. A first attempt to measure 92Nb/93Nb ratios with Accelerator Mass Spectrometry

    Science.gov (United States)

    Guozhu, He; Ming, He; Zuying, Zhou; Zhenyu, Li; Kejun, Dong; Shaoyong, Wu; Shilong, Liu; Xiongjun, Chen; Qiwen, Fan; Chaoli, Li; Xianwen, He; Heng, Li; Shan, Jiang

    2013-01-01

    An Accelerator Mass Spectrometry (AMS) method for the measurement of the long-lived radionuclide 92Nb has been established at the HI-13 Tandem Accelerator of the China Institute of Atomic Energy (CIAE). Niobium powder mixed with PbF2 by a ratio of 1:2 (in mass) was used as the cathode material. Atomic anions of Nb- were extracted from a Cs-beam sputter source. The terminal voltage of the tandem accelerator was 8.5 MV. Nb13+ ions were selected after terminal foil stripping. A multi-anode gas ionization chamber was used for the particle detection. The total suppression factor of the two major interfering isobars, 92Zr and 92Mo, was about 103. A detection limit of about 10-11 was achieved for 92Nb/93Nb ratio measurements on a blank sample.

  5. Up-grading of accelerating tube on HI-13 tandem accelerator

    International Nuclear Information System (INIS)

    The accelerating tube up-grading on HI-13 tandem accelerator at CIAE has been completed. The old 182.9 cm accelerating tubes which have been operated for more than 15 years were replaced by one 243.8 cm tube and seven 223.5 cm tubes. To accommodate the new tubes, the configuration of all elements along the beam axis inside tank was rearranged. The modifications on dead section structure, charging system and resistor dividing system has been made. The idlers for the laddertron charging system and resistor dividing system has been made. The idlers for the laddertron charging system were redesigned and manufactured. A new structure of the gridded lens at the entrance of tube No.1 and associated power supply and control system was adopted. The terminal voltage of the tandem accelerator is now promoted to 15.07 MV

  6. Advanced cement solidification technique for spent resins

    International Nuclear Information System (INIS)

    In the past 40 years, the nuclear facilities of China Institute of Atomic Energy (CIAE) produced an amount of radioactive organic resins, a kind of problematic stream in nuclear industry. As these facilities were stepping into decommissioning, the treatment of the spent organic resins was put on the agenda. The various routes for spent resin treatment such as incineration, advanced oxidation, cement immobilization, etc, were considered. Each method has its advantages and disadvantages when applied in the treatment of spent resins. Since the quantities of the spent organic resins were relatively small and an experience with variety of cementation processes existed in CIAE, predominately for immobilization of the evaporated concentrates, the option of direct encapsulation of the spent organic resins into cementitious materials was adopted in 2003, as a preferred method from the point of view of saving the on the cost of the disposal. In order to realize the end goal, the main work consisted of: the survey of the source terms; cementitious material formula investigation; and the process development. This work, which was undertaken in the following years, is addressed as follows. Source terms of the spent resins in CIAE were to be made clear firstly. The results showed that a total of 24-29 m3 of spent resins was generated and accumulated in the past 40 years. Spent resin arose from two research reactors (heavy water reactor and light water reactor), and from the waste management plant. The amount of the spent resins from the heavy water reactor was 1m3 or so, but its radioactive concentration was high to ∼108-∼109Bq/m3. Two kinds of cements, ASC and OPC cement were selected next, as the solidifying matrix to be investigated. A mixture surface response approach was employed to design experiment and interpret data. In comparison, ASC was superior to OPC cement and it displayed preferable performances to encapsulate spent resins. The optimum formulation is:1) resin

  7. MEASUREMENT OF PROMPT NEUTRON SPECTRA OF 238U FISSION INDUCED BY 10.17 AND 12.12 MeV NEUTRONS

    Institute of Scientific and Technical Information of China (English)

    李安利; 白希祥; 等

    1994-01-01

    Experimental method to measure the prompt neutron spectra of 238U fission induced by fast neutrons has been developed at HI-13 Tandem Van de Graaff Accelerator Laboratory of CIAE.These techniques employ a multi-segment fission chamber and two liquid scintillator neutron detectors.TOF(time of flight)techniques are used for primary neutrons to select the fission events induced by monoenergetic neutron from 2H(d,n) reactions instead of breakup neutrons from 2H(d,np) reactions.The fission neutron TOF spectra are measured in coincidence with the fission fragments to distinguish fission neutrons from other secondary neutrons.The method permits measurements to a fairly good accuracy under large neutron and gamma ray background.The techniques are described and experimental spectra are presented.

  8. High performance computation on beam dynamics problems in high intensity compact cyclotrons

    Institute of Scientific and Technical Information of China (English)

    ADELMANN; Andreas

    2011-01-01

    This paper presents the research progress in the beam dynamics problems for future high intensity compact cyclotrons by utilizing the state-of-the-art high performance computation technology. A "Start-to-Stop" model, which includes both the interaction of the internal particles of a single bunch and the mutual interaction of neighboring multiple bunches in the radial direction, is established for compact cyclotrons with multi-turn extraction. This model is then implemented in OPAL-CYCL, which is a 3D object-oriented parallel code for large scale particle simulations in cyclotrons. In addition, to meet the running requirement of parallel computation, we have constructed a small scale HPC cluster system and tested its performance. Finally, the high intensity beam dynamics problems in the 100 MeV compact cyclotron, which is being constructed at CIAE, are studied using this code and some conclusions are drawn.

  9. Retrieval and conditioning of high level radioactive solid waste from pit-type storage facilities

    International Nuclear Information System (INIS)

    A city radioactive waste temporary storage facility was operated for many years and aged seriously. In the 1970s, some high level radioactive solid waste (HLW) was stored in this facility because of bad management, which threatens the environment safety and should be retrieved and conditioned as soon as possible. According to the real condition in site, a retrieval technical process for HLW utilizing 'robot-airproof work cell' was employed the Department of Radioactive Waste Management, CIAE. The HLW was located in the No. 17 pit through contaminated level and detected hot-spot. After the mock-up test, the retrieval technical process was optimized. Finally, the HLW was successfully retrieved and conditioned in remote control way. (authors)

  10. MNSR transient analyses and thermal-hydraulic safety margins for HEU and LEU cores using PARET

    International Nuclear Information System (INIS)

    Thermal-hydraulic performance characteristics of Miniature Neutron Source Reactors under long-term steady-state and transient conditions are investigated. Safety margins and limiting conditions attained during these events are determined. Modeling extensions are presented that enable the PARET/ANL code to realistically track primary loop heatup, heat exchange to the pool, and heat loss from the pool to air over the pool. Comparisons are made of temperature predictions for HEU and LEU fueled cores under transient conditions. Results are obtained using three different natural convection heat transfer correlations: the original (PARET/ANL version 5), Churchill-Chu, and an experiment- based correlation from the China Institute of Atomic Energy (CIAE). The MNSR, either fueled by HEU or by LEU, satisfies the design limits for long-term transient operation. (author)

  11. A small angle neutron scattering study of thermoplastic elastomer

    Energy Technology Data Exchange (ETDEWEB)

    Sutiarso; Edy Giri, R. Putra; Andon, Insani; Sudirman; Sudaryanto [Materials Science Research Centre, National Atomic Energy Agency, Jakarta (Indonesia)

    1998-10-01

    A bilateral scientific cooperation, in the small angle neutron scattering has been agreed upon between CIAE, China and BATAN, Indonesia as well as MINT Malaysia. As stated in the agreed proposal that the objective of this cooperation, in the initial stage (stage-1), was to have a regional intercomparison measurements of SANS instruments in order to determine their characteristic/performance. Therefore, this report is supposed to describe the progress in the SANS instrument development of each country involved during the period of 1996/97 and some activities related to the SANS instrument. Since, up to now, we have not yet received any progresses reported from either China or Malaysia, this report will describe the progress of SANS`s activities in BATAN only. (author)

  12. The measurement of neutron energy response of the thin plastic scintillator using white neutron source

    International Nuclear Information System (INIS)

    At the HI-13 accelerator of CIAE, using D (d, n) break-up reaction,the experiment of neutron energy response of the thin plastic scintillator has been performed. The incident energy of D ions are three points of 9 MeV, 12 MeV, 14 MeV, and the neutron energy is between 0.75 MeV and 17 MeV. The intensity of neutron beam is measured by standard liquid scintillation detector at zero degree. The uncertainties of experimental results are discussed in detail. The experimental neutron response curves of the plastic scintillator show that the calculated energy response is in good agreement with the experimental data. (authors)

  13. Effect of microstructure changes on the mobility of radionuclides in simulated HLW ceramics

    International Nuclear Information System (INIS)

    Ceramic matrices for immobilization of HLW (e.g. perovskite, zirconolite, brannerite, zircon mineral based ceramics), prepared at ANSTO and C.I.A.E., respectively were characterized at the NRI Rez from the viewpoint of their microstructure and transport property changes caused by leaching. Scanning electron microscopy (SEM) and diffusion structural analysis (DSA) techniques were used. The thermal behavior of 'as leached' and 'as prepared' samples were compared. The DSA was used for the evaluation of atomic transport properties of the ceramic matrices. The effect of leaching on the thermal stability of the ceramics microstructure was characterized. The behaviour of the ceramic HLW matrices in simulated repository conditions was predicted by using the results of the mathematical modeling. (author)

  14. Status of R and D on tritium permeation barrier coatings for tritium breeding blanket of fusion reactor

    International Nuclear Information System (INIS)

    The paper overviews the recent progress in the application of several typical tritium permeation barrier (TPB) coatings and their corresponding fabrication technologies for tritium breeding blanket of fusion reactor. According to the design requirements of CN HCCB-TBM and DFLL-TBM. China Institute of Atomic Energy (CIAE) and cooperation u nits have made great progresses in TPB coatings on the Reduced Activation Ferritic/Martensitic (RAFM) steel substrate. Some typical TPB coatings, such as FeAl/Al2O3, Er2O3, Y2O3 and Al2O3, have been prepared by pack aluminizing plus pre-oxidizing, Sol-Gel and MOCVD processes. The results showed that all major properties, including micro- properties, gas permeation reduction factor, electrical insulation properties etc., meet basically the requirements. (authors)

  15. BN-600 hybrid core benchmark analyses (phases 1 and 2) (draft synthesis report)

    International Nuclear Information System (INIS)

    Tables of detailed calculation results submitted by eight participants (namely ANL, CEA/SA, CIAE, IGCAR, IPPE, JNC, KAERI, OKBM) of the CRP contain the following data: multiplication factor; Doppler coefficients for fuel and steel; reactivity density coefficient for sodium, steel and fuel; reactivity worth of absorption elements; expansion coefficients; power distribution in the core; reaction rate distributions. All the calculations were done for the chosen benchmark BN-600 reactor core. The report contains short description of the applied codes and nuclear data libraries used. The computer codes used for the cell calculations, i.e. calculations of effective cross sections applied Monte Carlo ultra fine method; subgroup method; f-factor method; collision probability method. Codes used for core calculations applied diffusion theory, transport theory, perturbation theory, Monte Carlo method using different condensed group constant sets

  16. 236U and its measurement with accelerator mass spectrometry

    International Nuclear Information System (INIS)

    236U is a long-lived radionuclide with half-life of 2.342(3) x 107 a. The ratio of 236U/238U is about 10-14 in the natural Uranium. The origin and production of 236U in globe are introduced and estimated in this paper, respectively. The major applications of 236U as a 100-million year neutron flux integrator, as a 'fingerprint' for monitoring nuclear environment and nuclear activity,and as a tracer in geological studies are briefly summarized. The accelerator mass spectrometry(AMS) measurement of 236U in the world and the research on HI-13 tandem accelerator at China Institute of Atomic Energy(CIAE) is also mentioned in this paper. (authors)

  17. Developing anti-metallic contamination polyester membranes with nuclear pore technique

    International Nuclear Information System (INIS)

    Surface contamination by conducting materials, metals in particular, is one of the important causes for electric breakdown of insulators under high voltage. In order to explore the feasibility of nuclear track modification for anti-metallic contamination, polyester membranes with different thickness were bombarded by 32S ions from the HI-13 tandem accelerator of CIAE. The tracks formed on the surface of the membranes were etched under different conditions. The insulating capability of the treated membranes was evaluated by using silver coatings to simulate the surface metallic contamination. The results indicated insulators with the surface modified by nuclear pore technique have an improved capability of anti-contamination of metals. The sample with 144 nm Ag coating is not breakdown under 1000 V. (authors)

  18. Integral experiment of large slab polyethylene samples with 14.8 MeV collimated neutron beams

    International Nuclear Information System (INIS)

    An experimental facility for measuring the secondary neutron emission spectra from slab sample with collimated D-T neutron source based on time-of-flight (TOF) technique has been established at China Institute of Atomic Energy (CIAE). The measurement of the neutrons leakage spectra from polyethylene slab samples of different thickness at 30° and 50° was carried out firstly. The measured results were compared with the calculated ones by MCNP simulation. The angle dependent neutron energy spectra of the neutron source, influence of the target material on the neutron source, width of pulse beam and detection efficiency were considered carefully in the simulation. The experimental results agree with the calculated results within the experimental uncertainties. (authors)

  19. BRIF and CARIF progress

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    China Institute of Atomic Energy (CIAE) is currently constructing Beijing rare ion beam facility (BRIF) and is proposing China advanced rare ion beam facility (CARIF). This paper is aiming at introducing the progress of BRIF project and the con ceptual design CARIF. The ISOL type facility BRIF under construction is composed of a 100 MeV 300 ?A proton cyclotron, an ISOL with mass resolution of 20000, and a super-conducting LINAC of 2 MeV/q, and will be commissioned in 2013. CARIF facility proposed is planned to use both ISOL and PF techniques. It is based on a China advanced research reactor CARR that was critical, with ISOL separation of fission fragment, post acceleration to 150 MeV/u, and fragmentation of neu tron-rich fission fragment beam like 132Sn. Such unique combination will allow CARIF to deliver beam intensity better than the best world facilities by more than one order of magnitude.

  20. The development for C-band whole sealed vacuum accelerating tuber

    International Nuclear Information System (INIS)

    S-Band standing wave electron linacs have got wide-ranging application for industry nondestructive testing and formed varied kinds of products. X-band electron linac for NDT has been developed by Schonberg Company USA in 1985. Because of bigger structure of S-band linac and difficult machining of X-Band linac, an C-band portable linac for NDT has been developed in CIAE at present, a whole sealed vacuum accelerating tuber will be given here. It consists of 4 cavities, the phase velocity of the first two cavities is 0.5 and 0.9, respectively, and that of the second two cavities is 1. The high power testing proved that the design of the accelerating tuber is good for 1.5 MeV electron linac for NDT

  1. ADS National Programmes: China

    International Nuclear Information System (INIS)

    In China the conceptual study of an ADS concept which lasted for about five years ended in 1999. As one project of the National Basic Research Programme of China (973 Programme) in energy domain, which is sponsored by the China Ministry of Science and Technology (MOST), a five year programme of fundamental research of ADS physics and related technology was launched in 2000 and passed national review at the end of 2005. From 2007, another five year 973 Programme Key Technology Research of Accelerator Driven Subcritical System for Nuclear waste Transmutation started. The research activities were focused on HPPA physics and technology, reactor physics of external source driven subcritical assembly, nuclear data base and material study. For HPPA, a high current injector consisting of an ECR ion source, LEBT and an RFQ accelerating structure of 3.5 MeV has been built and were being improved. In reactor physics study, a series of neutron multiplication experimental study has been carrying out. The VENUS I facility has been constructed as the basic experimental platform for neutronics study in ADS blanket. VENUS I a zero power subcritical neutron multiplying assembly driven by external neutron produced by a pulsed neutron generator or 252Cf neutron source. The theoretical, experimental and simulation studies on nuclear data, material properties and nuclear fuel circulation related to ADS are carried out in order to provide the database for ADS system analysis. China Institute of Atomic Energy (CIAE), Institute of High Energy Physics (IHEP) and other Chinese institutes carried out the MOST project together. Besides CIAE, China Academy of Science (CAS) pays more and more attention to Advanced Nuclear Fuel Cycles (ANFC). A large programme of ANFC, including ADS and Th based nuclear fuel cycle, has been launched by CAS

  2. Study of mechanism of cancer caused by carcinogenic substances with accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Full text: It is reported that most of the cancerous patients were caused by cancerogenic substances. The research in recent years shows that carcinogenesis is related with Ca in the cells. In normal cells, the level of free Ca2+ is very stable, the Ca2+ as messenger plays an important role to keep normal function of cells. However, the level of free Ca2+ in cells increases when the cells are exposed to cancerogenic substances such as cigarette smoking solution and chrysotile. But where do the increased Ca2+ come from? There are three possibilities: 1) from outside of cell membrane; 2) from inside of nucleus; or 3) from both outside and inside of cells. By using external cultivation of cells 41Ca as tracer and accelerator mass spectrometry (AMS) as measurement method, we investigate the origin of the increased Ca2+ when the cells are exposed to cigarette smoking solution or chrysoltile is being undertaken. Several results as below have been gotten. 1. 41Ca synthesis. A high purification of isotope of 40Ca (99.95%) in form of CaO was irradiated by thermal neutron with a heavy water reactor at the China Institute of Atomic Energy (CIAE). The irradiation time and neutron flux were 988h and 4.9x1013, respectively. A 41Ca/40Ca ratio of 7x10-5 was obtained. The conversion efficiency of Ca metal to CaH2 was 80% to 90%. 2. CaH2 sample preparation. There are two steps for CaH2 sample preparation in AMS measurement. In the first step, CaO is reduced to metallic calcium via vacuum distillation and in the second, the CaO is converted into a hybrid. 3. 41Ca AMS measurement. The first 41Ca AMS measurement was performed with Hl-13 tandem AMS system in the CIAE. By using a 41Ca blank sample, 30 nA of CaH3- ions from ion source can be obtained. Ions were accelerated with a terminal voltage of 7.8 and Ca8+ (E=69.7 MeV) ions were selected. From the measurement, a 41Ca/40Ca ratio of about 10-14 was deduced. (author)

  3. A novel cytologic sampling technique to diagnose subclinical endometritis and comparison of staining methods for endometrial cytology samples in dairy cows.

    Science.gov (United States)

    Pascottini, O B; Dini, P; Hostens, M; Ducatelle, R; Opsomer, G

    2015-11-01

    The present article describes a study of the diagnosis of subclinical endometritis in dairy cows having two principal aims: first, to validate a novel technique for taking endometrial cytology samples to diagnose subclinical endometritis in dairy cows. Second, to compare the percentage of polymorphonuclear cells (PMNs) in cytology samples stained with Diff-Quik versus a specific staining method for PMNs, naphthol-AS-D-chloroacetate-esterase (CIAE). In the first experiment, Holstein-Friesian cows (n = 204) were used to take two cytology samples at the same time using the conventional cytobrush (CB) and the new cytotape (CT). Both devices were assembled within the same catheter allowing sampling at the same time, and approximately at the same location. Cytotape consisted of a 1.5-cm piece of paper tape rolled on the top of an insemination catheter covered with a double guard sheet. Parameters used to evaluate both methods were: PMNs percentage, total cellularity, quality of the smears, and red blood cell contamination. The concordance correlation coefficient analysis was used to assess agreement between continuous and Pearson chi-square tests for categorical variables. Agreement between the percentage of PMNs in both methods was good ρ = 0.84 (0.79, 0.87) with a minor standard error of 2%. Both methods yielded similar total cellularity (P = 0.62). Cytotape yielded better quality smears with more intact cells (P < 0.01) while samples that were taken by CB were more likely to be bloody (P < 0.01). Hence, CT and CB methods yielded smears with a similar PMNs percentage and a total number of cells, but CT provided smears with higher quality and significantly less blood contamination. For the second experiment, 114 duplicate cytology slides were stained using both Diff-Quik and CIAE. Agreement between PMNs percentage in both staining techniques was good ρc = 0.84 (0.78, 0.89) with a standard error of only 2%. Hence, Diff-Quik was confirmed as an easy, fast

  4. ISP-50 Specifications for a Direct Vessel Injection Line Break Test with the ATLAS

    International Nuclear Information System (INIS)

    An OECD/NEA International Standard Problem Exercise (ISP) focussing on a DVI line break simulation result with the ATLAS was approved by the NEA Committee on the Safety of Nuclear Installation (CSNI) meeting in December 2008 and was numbered by ISP-50. The ISP-50 program will be operated by an operating agency, KAERI for three years starting from the physical year 2009. Fourteen international organizations confirmed their participation in the ISP-50, including NRC (USA), JAEA, JNES (Japan), GRS (Germany), KFKI-AEKI (Hungary), EDO Gidropress (Russia), VTT, Fortum (Finland), NRI (Czech Republic), Univ. of Pisa (Italy), KINS, KNF, KOPEC, and KAERI (Korea). In addition, KTH in Sweden and HSE in UK are considering late participation. Recently, NPIC and CIAE in China hope to join the ISP-50. As for the safety analysis codes, nine codes are expected to be used for the ISP-50: MARS-3D, RELAP5- 3D, RELAP5, TRACE, CATHARE, APROS, ATHELET, TRAP, and KORSAR. It is the first ISP exercise in Korea in which a domestic test facility is utilized by international nuclear society and this exercise will contribute to extending our physical understanding on thermal hydraulic phenomena during the DVI line break accidents and to verifying the best-estimate thermal-hydraulic safety analysis codes. This report was prepared to define technical specifications of the ISP-50 exercise according the guideline provided by OECD/CSNI. It includes general objectives, phases, deliverables to participants, parameters required for comparison and the time table

  5. The development of electron linacs with high energy and high power for the purpose of irradiation processing

    International Nuclear Information System (INIS)

    Electron linacs are the key devices for the irradiation processing industrialization in the application of nuclear technology. Therefore the R and D of electron linacs is very important. A 10 MeV 15 kW class electron linac for sterilization of medical devices and food has been designed and built at CIAE and HTA. The details of it are presented in this paper. The accelerator facility has been used for different food commodities treatment for about two years, which demonstrated that it is a very successful new type of device for irradiation processing. During the R and D of the accelerator facility, we developed some key technology such as the accelerating, transportation and extraction of high intensity electron beams, the design and manufacture of high voltage pulse modulator with high power and long pulse, and the high power stable operation of the accelerator facility. We promote the technology of electron linacs for irradiation processing in china and this upgrades chinese manufacture technique and the industrialization capability of this type of accelerator facility. (authors)

  6. Measurement of fission product nuclide 126Sn with accelerator mass spectrometry based on SnF2 target

    International Nuclear Information System (INIS)

    A new analytical method, using SnF2 target and extracting SnF3- molecular negative ions, was developed at CIAE HI-13 Accelerator Mass Spectrometry System for measurement of 126Sn. The development of the 126Sn calibration standard for AMS measurement and the preparation flow of target materials SnF2 were described in this paper. The results indicate that the extraction ion form SnF3- can depress the interference of 126Te as much as 2-3 order of magnitude. A perfect linearity (R2=0.999) between measured and nominal 126Sn/Sn atom number ratios was obtained by using three standard samples with 126Sn/Sn atom number ratios of 1.033 ×10-8, 4.54 ×10-9, and 6.43 ×10-10. A sensitivity of (1.92±1.13) ×10-10 (126Sn/Sn) was reached by measuring a blank sample. (authors)

  7. Initiatory pathologic observation of proton-irradiated mice's organs

    International Nuclear Information System (INIS)

    Space radiation come from galactic cosmic rays and solar particle events which contain considerable protons is an invisible killer to astronauts. Furthermore, many wounded persons were injured by proton and other heavy ion radiation in a nuclear warhead or nuclear terrorism attack. However, the damage effect of proton radiation is known little in our country. In this study, the proton induced histopathologic changes of mice were observed primarily. Anaesthetic mice were irradiated with the 19 MeV protons dilivered by HI-13 tandem accelerator at CIAE in different doses (2,4,8,16 Gy). In order to observe the damage effect, mice were killed by anaesthetic at different time point after radiation, and the tissue sections were analyzed by a histopathologic method. The results show that all of the mice's backs began displaying ringed depilation at post-irradiation day 7. Many epidermal cells necrosis and exfoliation happened, and subcutaneous dropsy was observed. There were some focal necrosis or even followed with bleeding in heart and liver. Hepatocyte evidently regenerated. A hyperaemia was seen in lung tissue and alveolar septum was obviously thickening. Acinus renis represented notable pyknosis, necrosis and disappearance. Especially, these pathologic alteration clearly displayed in high dose groups. In conclusion, proton-radiation can induce different grade injury to skin, heart, liver, lung, kidney and other organs. Further studies should be made to deeply understand the mechanism about the proton radiation damage. (authors)

  8. Investigation of the immobilization of the radioactive ion exchange resins into specific cement using the mixture response surface approach

    International Nuclear Information System (INIS)

    This study was conducted to assess a kind of specific cement (ASC) extensively and recommend a suitable formula for the immobilization of the radioactive ion exchange resins from China Institute of Atomic Energy (CIAE). A mixture response surface approach was employed to design the experiment and interpret the results. Compared with the blend composed of ordinary Portland cement (OPC), an optimum combination, resin: .17 (dry wt/wt); ASC: .43; zeolite: .10, and water: .30, was determined within a series of restrictions for such properties as the slump, the 28-d compressive strength, the water immersion, the thaw-freeze resistance, the irradiation resistance, and the leaching rate. The diffusivities of 137Cs and 60Co of the waste forms resulting from the formula were 2.72E-06 (cm2/d) and 1.63E-07 (cm2/d) after 123 d, respectively. The loading amount of spent resins in the ASC form was larger than that in the OPC form by 5% under the equal performance indexes. The microanalysis indicated that there were many interlaced columnlike crystals (ettringites) developed in ASC-resin concrete. This structure could enhance the strength and stabilization of the waste forms significantly. (author)

  9. Unprotected Overpower Transient Analysis of CEFR Core Using the SAS4A-SASSYS-1 Code

    International Nuclear Information System (INIS)

    In order to investigate China Experimental Fast Reactor (CEFR) core performance during unprotected transient overpower (UTOP) accidents, postulated control rod withdrawal accidents have been simulated and analyzed using the SAS4A/SASSYS-1 code. Researchers at China Institute for Atomic Energy (CIAE) performed the SAS4A safety analyses of CEFR in collaboration with Argonne National Laboratory (ANL) researchers. This collaboration is carried out within the framework of the Fast Reactor Technology Working Group of the U.S. – China Bilateral Civil Nuclear Energy Cooperation. Assumptions were made for the UTOP accidents that lead to relatively large reactivity insertions. The change of reactor reactivity and power as well as the fuel, cladding, and coolant temperatures during the transient process were analyzed in order to characterize the accident sequence. Accident consequences were studied with a focus on fuel and cladding melting and relocation behavior. The effects of different reactivity feedback mechanisms on the reactor power history during the transients were analyzed. The results showed that the negative reactivity feedback due to coolant temperature change and coolant voiding played an important role in counteracting the effects of the inserted positive reactivity. The simulation demonstrated the inherent safety characteristics of the CEFR core, which exhibits negative reactivity feedbacks during UTOP transients. (author)

  10. Study on bone resorption behavior of osteoclast under drug effect using {sup 41}Ca tracing

    Energy Technology Data Exchange (ETDEWEB)

    Dong Kejun [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Lu Liyan [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); CNNC Third Qinshan Nuclear Power Co. Ltd., Haiyan 314300 (China); He Ming; Ouyang Yinggen; Xue Yan; Li Chaoli; Wu Shaoyong [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Wang Xianggao [College of Physics Science and Technology, Guangxi University, Nanning 530004 (China); Shen Hongtao [College of Physics and Technology, Guangxi Normal University, Guilin 541004 (China); Gao Jianjun [Institute of Radiation Medicine, Fudan University, Shanghai 200032 (China); Wang Wei [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); China National Nuclear Corporation, Beijing 100822 (China); Chen Dafu; Xing Yonggang [Beijing Research Institute of Traumatology and Orthopaedics, Beijing 100035 (China); Jian, Yuan [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Jiang Shan, E-mail: jiangs@ciae.ac.cn [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China)

    2013-01-15

    The mechanisms governing calcium fluxes during bone remodeling processes in Osteoporosis (OP) patients are poorly known. Understanding the changes of Osteoclasts (OC) during this dynamic transition is important to prevent and cure OP. The exploration of long-lived {sup 41}Ca (T{sub 1/2} = 1.04 Multiplication-Sign 10{sup 5} years) tracer combined with AMS measurements leads to the possibility of monitoring the bone resorption behavior of OC in OP patients. In this work, the behavior of OC with the administration of Strontium Ranelate (SR), a drug for OP, was studied by using {sup 41}Ca labeled hydroxyapatite (HAP) to simulate the bone. AMS on the HI-13 tandem accelerator at CIAE was used to determine trace amounts of {sup 41}Ca. The results show that the technique of {sup 41}Ca tracing with AMS can be used to quantitatively monitor the behavior of OC in bone resorption under the effects of drugs. Experimental details and preliminary results will be presented.

  11. Ten years' operation maintenance and improvement of the HI-13 tandem accelerator

    International Nuclear Information System (INIS)

    The HI-13 tandem accelerator at CIAE has been running for more than ten years since it was put into normal operation in august 1987. The accumulated operation time and beam time is about 40000 and 35000 h, respectively. The machine now is still in good technical condition with highest terminal voltage of 12.7 MV with beam and beam time of more than 3500 h per year in recent years. The completely home-made laddertron for the machine has been in operation for near 8000 h with good performance. The original 'blue resistors' made by HVEC in the high voltage divider system of the HI-13 tandem accelerator have been completely replaced by the resistors with framework which are completely home-made and the performances of the resistors are satisfactory. To meet the requirements of the experiments, five additional beam lines were built up in the past ten years making the total number of the beam lines in the laboratory up to eleven and some other improvements on the machine have also been done

  12. The physics experimental study for in-hospital neutron irradiator

    International Nuclear Information System (INIS)

    MNSRs (Miniature Neutron Source Reactor) are low power research reactors designed and manufactured by China Institute of Atomic Energy (CIAE). MNSRs are mainly used for NAA, training and teaching, testing of nuclear instrumentation. The first MNSR, the prototype MNSR, was put into operation in 1984, later, eight other MNSRs had been built both at home and abroad. For MNSRs, highly enriched uranium (90%) is used as the fuel material. The In-Hospital Neutron Irradiator (IHNI) is designed for Boron Neutron Capture Therapy (BNCT) based on Miniature Neutron Source Reactor(MNSR). On both sides of the reactor core, there are two neutron beams, one is thermal neutron beam, and the other opposite to the thermal beam, is epithermal neutron beam. A small thermal neutron beam is specially designed for the measurement of blood boron concentration by the prompt gamma neutron activation analysis (PGNAA). In this paper, the experimental results of critical mass worth of the top Be reflectors worth of the control rod, neutron flux distribution and other components worth were measured, the experiment was done on the Zero Power Experiment equipment of MNSR. (author)

  13. Research on high spin structures of N=79 isotones in A=135 nuclear region

    International Nuclear Information System (INIS)

    The progress of research on the high spin states at N=79 isotopes 135Ba, 137Ce and 139Nd in A=135 neutron-deficient region by the research group of Tsinghua University has been reviewed. The experiments were carried out by using in-beam γ-ray spectroscopy technology and heavy ion nuclear reactions 130Te(9Be, 4n), 124Sn(18O, 5n) and 128Te(16O, 5n) at China Institute of Atomic Energy (CIAE). The high spin level schemes of these nuclei have been expanded. The results indicate that the lower spin states of these nuclei originated from νh11/2-1 hole state coupling with the neighboring even-even nucleus cores. All the deformation parameters γ values of these three isotones are larger than 30 degree, which indicates that they have triaxial deformation with oblate side. The prolate-oblate transition in Ba, Ce and Nd isotopic chains indeed happens between N=77 and N=79. Through systematical comparison with the neighboring isotones, the configurations for some middle spin state levels have been assigned. At the high spin states, one oblate band in 137Ce and three ones in 139Nd with γ≅-60 degree were discovered. The origination and structural character of these oblate bands have been discussed. (authors)

  14. Physics design of CYCAIE-100

    Institute of Scientific and Technical Information of China (English)

    ZHANG Tian-Jue; LI Zhen-Guo; ZHONG Jun-Qing; AN Shi-Zhong; YAO Hong-Juan; JI Bin; WEI Su-Min; GUAN Feng-Ping; YANG Jian-Jun; BI Yuan-Jie; JIA Xian-Lu; WANG Chuan

    2009-01-01

    The design and construction of Beijing Radioactive Ion-beam Facility(BRIF)was started at China Institute of Atomic Energy-CIAE)in 2004.In this project,a 100 MeV high intensity cyclotron,CYCIAE100,is selected as a driving accelerator for radioactive ion beam production.It will provide a proton beam of 75-100 MeV with an intensity of 200-500 μA.The scheme adopted in this design,i.e.,stripping the for each system has been accomplished.This paper depicts the basic physics design of the machine,including its major structure and parameters,beam dynamics and each relevant system,e.g.basic structure of the main magnet,numerical simulation of the RF resonant cavity,axial injection system,central region,and study on crucial physics problems concerning the extraction and beam lines.The major problems encountered during the design of CYCIAE-100 are also summarized in this paper.

  15. Production of 62Zn radioactive nuclear beam and on-line PAC investigation of quadrupole interaction in nano-magnetic material Fe73.5Cu1Nb3Si13.5B9

    International Nuclear Information System (INIS)

    An Isotope Separator On-Line (ISOL), dedicated to on-line perturbed angular correlation (PAC) and positron annihilation spectroscopy (PAS), has been constructed at CIAE based on the HI-13 tandem accelerator, and a 30 keV radioactive beam of 62Zn with intensity of 2 ×107/s produced by it. Using the 62Zn radioactive beam the investigation of the nano-crystalline soft magnetic Fe73.5Cu1Nb3Si13.5B9 materials has been fulfiled for the first time by the on-line time differential PAC technique. Two quadrupole interaction frequencies ω01 ( = 440 Mrad/s) and ω02 ( = 90 Mrad/s) were gained, indicating there are two implantation sites of 62Zn. The frequency ω02 shows a fluctuation of the crystal lattice constants and proves the characteristic distribution model of nano-crystalline grain boundary. The frequency ω01 demonstrates that the implanted 62Zn occupies the site of the ordered grain core. The fractions of ω01 and ω02 are f01 = 38 % and f02 = 62 %, respectively.

  16. The status of facilities at China Advanced Research Reactor

    International Nuclear Information System (INIS)

    A 60 MW research reactor, so called China Advanced Research Reactor (CARR,) was built in China Institute of Atomic Energy (CIAE), located in the southwest of Beijing and about 37 kilometers away from the central city. CARR is a tank-in-pool inverse neutron trap type reactor using D2O reflector, the designed optimal undisturbed thermal neutron flux is 8×1014 n⋅cm-2⋅s-1. A liquid D2 cold source will be equipped and the installation will be finished at the end of 2015. As a multipurpose research reactor, its main applications include neutron scattering, neutron activation analysis, isotope production, silicon doping, fuel element test, fundamental nuclear physics and so on. On March 13rd, 2012 CARR realized the 72 h stable operation with the full power. And the official operation license is expected to be issued at the beginning of next year. Cooperating with the internal and international users in the first phase ten instruments complete construction and are under commissioning, which are High Resolution Powder Diffractometer, High Intensity Powder Diffractometer, Residual Stress Diffractometer, Texture Diffractometer, Four Circle Diffractometer, Reflectometer, Small Angle Neutron Scattering, two Thermal Triple Axis Spectrometers and Isotope Separator On-Line instrument . In the second phase 7 instruments were approved and are under construction now. Although the operation license was not issued, the reactor was permitted to do the testing run several times and some results were obtained during the instrument commissioning.

  17. Research co-ordination meeting on updated codes and methods to reduce the calculational uncertainties of liquid metal fast reactor reactivity effects. Working material

    International Nuclear Information System (INIS)

    The main purpose of the second RCM of the CRP on 'Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects' was to present and discuss the results of Phases 1 and 2 of the CRP and to agree on the work plan for Phase 3. The RCM considered: The presentation of work performed under Phase 1 and 2 of the CRP by CIAE (China), AEAT/CEA joint European contribution), IGCAR (India), JNC (Japan), KAERI (Republic of Korea), OKBM and IPPE (Russia), and ANL (USA); A preliminary analysis of the results from Phases 1 and 2; The definition of the work to be performed under Phase 3 of the CRP; A discussion of the Phase 4 CRP work scope. Calculation results of the proposed benchmark for a hybrid UOX/MOX fuelled core of the BN-600 reactor are resented. The calculation results of all the participants include effective multiplication factors obtained by both diffusion and Monte Carlo methods; fuel Doppler constants; steel Doppler constants; sodium density coefficient; steel density coefficients; fuel density coefficient; absorber density coefficient; axial and radial expansion coefficients; dynamic parameters; power distribution

  18. Mockup tests for developing the CARR-CNS with a two-phase thermo-siphon loop

    Institute of Scientific and Technical Information of China (English)

    DU She-Jiao; BI Qin-Cheng; CHEN Ting-Kuan; FENG Quan-Ke; LI Xiao-Ming

    2004-01-01

    The cold neutron source (CNS) is a facility to increase cold neutrons by scattering thermal neutrons in liquid hydrogen or deuterium around 20 K. For extracting a stable cold neutron flux fiom the CNS, the liquid quantity in the moderator cell should be maintained stably against disturbance of nuclear heating. The China Institute of Atomic Energy (CIAE) is now constructing the China Advanced Research Reactor (CARR: 60 MW), and designing the CARR-CNS with a two-phase thermo-siphon loop consisting of a condenser, two moderator transfer tubes and an annular cylindrical moderator cell. The mock-up tests were carried out using a full-scale loop with Freon-113, for validating the self-regulating characteristics of the loop, the void fraction less than 20% in the liquid hydrogen of the moderator cell, and the requirements for establishing the condition under which the inner shell has only vapor. The density ratio of liquid to vapor and the volumetric evaporation rate due to heat load are kept the same as those in normal operation of the CARR-CNS. The results show that the loop has the self-regulating characteristics and the inner shell contains only vapor, while the outer shell liquid. The local void fraction in the liquid increases with increasing of the loop pressure.

  19. Spin Structure of the Nucleon - Proceedings of the Riken Symposium

    Science.gov (United States)

    Shibata, S.; Ohta, N.; Saito, T.-A.

    1996-08-01

    The Table of Contents for the full book PDF is as follows: * Organizing Committee * Foreword * Theoretical Overview * The Context of High Energy QCD Spin Physics * Experimental Studies I * PHENIX and Spin Physics * RHIC Spin Project - Acceleration of Polarized Protons * CIAE Activities for the PHENIX Experiment * Spin Physics with PHENIX Detector System at RHIC * Experiments on Spin-dependent Structure Functions of the Nucleon * Measurements of the Spin-dependent Structure Function of the Nucleon at the Spin Muon Collaboration * Theoretical Studies * Higher-twist Effects in Spin Structure Functions * Light Hadrons from Lattice QCD in a (2.4 fm)3 Box at 4-GeV Cutoff * Tensor Charge of the Nucleon on the Lattice * Perturbative QCD Study on the Chiral-Odd Twist-3 Structure Function: hL(x,Q2) * Strange Matrix Elements of the Proton and Instantons in QCD * Experimental Studies II * Proton Structure Functions from ZEUS * Measurements of the Photon Structure Functions F_{2}^γ * Constraint on the Proton Structure from CDF: Lepton Charge Asymmetry in W Decays * A Search for Jet Handedness in Hadronic Z0 Decays * Concluding Remarks * High Energy Spin Physics - Past, Present and Future * Program

  20. The deuteron accelerator preliminary design for BISOL

    Science.gov (United States)

    Peng, S. X.; Zhu, F.; Wang, Z.; Gao, Y.; Guo, Z. Y.

    2016-06-01

    BISOL, which was named as Beijing_ISOL before (Cui et al., 2013), is the abbreviation of Beijing Isotope-Separation-On-Line neutron beam facility. It is proposed jointly by Peking University (PKU) and China Institute of Atomic Energy (CIAE) for basic science study and application. It is a double driven facility that can be driven by a reactor or a deuteron accelerator. The deuteron driver accelerator should accelerate the deuteron beam up to 40 MeV with maximum beam current of 10 mA. Proton beams up to 33 MeV and He2+ beams up to 81.2 MeV can also be accelerated in this accelerator. The accelerator can be operated on either CW (continuous waveform) or pulsed mode, and the ion energy can be adjusted in a wide range. The accelerator will also allow independent operation of the RIB (Radioactive Ion Beams) system. It will be mainly charged by PKU group. Details of the deuteron accelerator preliminary design for BISOL will be given in this paper.

  1. Simulation and analysis of 13N+p elastic resonance scattering

    Institute of Scientific and Technical Information of China (English)

    WANG You-Bao; QIN Xing; WANG Bao-Xiang; LIU Wei-Ping; LI Zhi-Hong; BAI Xi-Xiang; LIAN Gang; GUO Bing; ZENG Sheng; SU Jun; LI Yun-Ju; JIANG Chao

    2009-01-01

    The 13N+p elastic resonance scattering has been studied at the secondary radioactive beam facility of CIAE in inverse kinematics via a thick-target method. The excitation function for the 13N(p,p) scattering was obtained in the energy interval of Ecm ≈0.5--3.2 MeV with a 13N secondary beam of (47.8±1.5) MeV. Carefulanalysis of the secondary beam components and extensive Monte-Carlo simulations enable the resolution of the experimental proton spectra. The resonance parameters for five low-lying levels in 140 were deduced by R- matrix fitting calculations with MULTI7 and SAMMY-M6-BETA. The present results show general agreement with those from a recent similar work, and thus confirm the observation of a new 0- level at 5.7 MeV in 14O with an improved width of 400(45) keV.

  2. International key comparison of measurements of neutron source emission rate (1999-2005): CCRI(III)-K9.AmBe

    International Nuclear Information System (INIS)

    Section III (neutron measurements) of the Comite Consultatif des Rayonnements Ionisants, CCRI, conducted a key comparison of primary measurements of the neutron emission rate of an 241Am-Be(α,n) radionuclide source. A single 241Am-Be(α,n) source was circulated to all the participants between 1999 and 2005. Eight laboratories participated - the CIAE (China), CMI (Czech Republic), KRISS (Republic of Korea), LNMRI (Brazil), LNE-LNHB (France), NIST (USA), NPL (UK) and the VNIIM (Russian Federation) - with the NPL making their measurements at the start and repeating them near the end of the exercise to verify the stability of the source. Each laboratory reported the emission rate into 4π sr together with a detailed uncertainty budget. All participants used the manganese bath technique, with the VNIIM also making measurements using an associated particle technique. The CMI, KRISS, VNIIM, and later the NPL, also measured the anisotropy of the source although this was not a formal part of the comparison. The first draft report was released in May 2006 and having been discussed and modified by the participants and subsequently reviewed by the CCRI(III), the present paper is now the final report of the comparison. (authors)

  3. New measurement of $\\rm S_{bare}(E)$ factor of the d(d,p)t reaction at astrophysical energies via the Trojan-horse method

    CERN Document Server

    Li, Chengbo; Fu, Yuanyong; Zhou, Jing; Zhou, Shuhua; Meng, Qiuying; Spitaleri, C; Tumino, A; Pizzone, R G; Lamia, L

    2015-01-01

    The study of d(d,p)t reaction is very important for the nucleosynthesis in both standard Big Bang and stellar evolution, as well as for the future fusion reactor planning of energy production. The d(d,p)t bare nucleus astrophysical S(E) factor has been measured indirectly at energies from about 400 keV down to several keV by means of the Trojan horse method applied to the quasi-free process $\\rm {}^2H({}^6Li,pt){}^4He$ induced at the lithium beam energy of 9.5 MeV, which is closer to the zero quasi-free energy point, in CIAE HI-13 tandem accelerator laboratory. An accurate analysis leads to the determination of the d(d,p)t $\\rm S(E)$ factor $\\rm S_{bare}(0)=56.7 \\pm 2.0 keV*b$ and of the corresponding electron screening potential $\\rm U_e = 13.2 \\pm 4.3 eV$. In addition, this work also gives an updated test for the Trojan horse nucleus invariance comparing with previous indirect investigations using $\\rm {}^3He=(d+p)$ breakup.

  4. Study of energy deposition and stripper temperature for CYCIAE-100

    Institute of Scientific and Technical Information of China (English)

    WEI Su-Min; ZHANG Tian-Jue; AN Shi-zhong; BI Yuan-Jie

    2009-01-01

    Nowadays high intensity proton accelerators are extensively applied,and this paper gives particular emphasis on CYCIAE-100,a 100 MeV high intensity compact cyclotron being constructed at CIAE.For accelerators of this type,the study is focused on how to improve the beam intensity.As for CYCIAE-100,the charge-exchange extraction is used to get protons.So it is crucial to enhance the lifetime of the stripping foil,which is largely determined by the energy deposition on it.For this cyclotron,due to the influence of the magnetic field.the electrons will spin near the foil and lose energy each time when they cross the foil.The energy deposition refers to all the energy deposition of protons and electrons.This paper stresses the stripper study of CYCIAE-100,in which the particle distribution on the foil is simulated and the energy deposition of calculated as a main reference for the foil design.

  5. 50 mm Diameter digital DC/pulse neutron generator for subcritical reactor test

    International Nuclear Information System (INIS)

    A 50 mm diameter digital DC/pulse neutron generator was developed with 25 mm ceramic drive-in target neutron tube. It was applied in the subcritical reactor test of China Institute of Atomic Energy (CIAE). The generator can produce neutron in three modes: DC, pulse and multiple pulse. The maximum neutron yield of the generator is 1 × 108 n/s, while the maximum pulse frequency is 10 kHz, and the minimum pulse width is 10 μs. As a remote controlled generator, it is small in volume, easy to be connected and controlled. The tested results indicate that penning ion source has the feature of delay time in glow discharge, and it is easier for glow discharge to happen when switching the DC voltage of penning ion source into pulse. According to these two characteristics, the generator has been modified. This improved generator can be used in many other areas including Prompt Gamma Neutron Activation Analysis (PGNAA), neutron testing and experiment.

  6. Fast Reactor Development Strategy in China

    International Nuclear Information System (INIS)

    As one of the largest developing countries, China needs a reliable energy supplement. At the same time, China should improve the energy structure to decrease CO2 emissions. Nuclear and renewable energies are the main solutions to these issues. According to the research results, the nuclear capacity should increase to 400 GW(e) up to 2050. Fast reactors must be developed considering the limitation of uranium resources. In order to deploy fast reactor technology, the ‘experimental reactor, demonstration reactor and commercial reactor’ strategy has been suggested. China has finished the construction of the China Experimental Fast Reactor (CEFR) and gained necessary experience about fast reactors. The China Institute of Atomic Energy (CIAE) has begun to design the CFR-600, a 600 MW(e) demonstration fast reactor. This reactor will be put into operation before 2025. After that, a larger commercial reactor will be constructed. Besides fast reactors, all of other key sectors of fuel cycle will be developed at the same time such as reprocessing, fast reactor fuel, etc. There are two main tasks of fast reactors, one of which is to raise the utility ratio of uranium, and the other one is to transmute the long life waste of light water reactors. The fast reactor will be designed as a breeder and burner, respectively. (author)

  7. Methodological study on exposure date of Tiankeng by AMS measurement of in situ produced cosmogenic {sup 36}Cl

    Energy Technology Data Exchange (ETDEWEB)

    Dong Kejun [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Li Shizhuo [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); CNNC China North Nuclear Fuel Company Ltd., Baotou 014035 (China); He Ming [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Sasa, Kimikazu [Tandem Accelerator Complex, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan); Matsushi, Yuki [Disaster Prevention Research Institute, Kyoto University (Japan); Huang Baojian [Institute of Karst Geology, Chinese Academy of Geological Sciences, Guilin 541004 (China); Ruan Xiangdong; Guan Yongjing [College of Physics Science and Technology, Guangxi University, Nanning 530004 (China); Takahashi, Tsutomu [Tandem Accelerator Complex, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan); Sueki, Keisuke [Graduate School of Pure and Applied Sciences, University of Tsukuba (Japan); Li Chaoli; Wu Shaoyong [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Wang Xianggao [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); Institute of Karst Geology, Chinese Academy of Geological Sciences, Guilin 541004 (China); Shen Hongtao [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China); College of Physics and Technology, Guangxi Normal University, Guilin 541004 (China); Nagashima, Yasuo [Tandem Accelerator Complex, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan); Jiang Shan, E-mail: jiangs@ciae.ac.cn [China Institute of Atomic Energy, P.O. Box 275(50), Beijing 102413 (China)

    2013-01-15

    Tiankeng is a typical Karst relief of the late Quaternary Period. Studies on the exposure ages of Tiankeng are very important in geographical research to elucidate the formation condition, the developing process, and the features of biological species. {sup 36}Cl on the surface layer of the rupture cross-section of Tiankeng is largely produced by cosmogenic high-energy neutron induced reactions {sup 40}Ca(n, {alpha}p) and {sup 39}K(n, {alpha}), and has accumulated since the formation of the Tiankeng. Low-energy neutron reaction {sup 35}Cl(n, {gamma}) contributes a small portion of {sup 36}Cl. In this work, the concentration of the cosmogenic {sup 36}Cl in rock samples taken from Dashiwei Tiankeng, Leye County, Guangxi Zhuang Autonomous Region, China, was measured jointly by Accelerator Mass Spectrometry (AMS) laboratories of CIAE and University of Tsukuba in an effort to estimate the formation time (or exposure age) of the Tiankeng. The results show that the exposure time of Da Shiwei Tiankeng is about 26 {+-} 9.6 ka (without erosion correction). The sampling strategy and procedures, experimental set-up, and preliminary results will be presented in detail.

  8. Shape Evolution in Rotating 178Os

    Institute of Scientific and Technical Information of China (English)

    HAO Xin; ZHU Li-Hua; WU Xiao-Guang; HE Chuang-Ye; ZHENG Yun; LI Li-Hua; SUN Hui-Bin; LI Guang-Sheng

    2011-01-01

    In order to investigate the evolution of X(5) in rotating 178Os, an experiment populating 178Os via the fusion evaporation reaction 154Sm(29si,5n)178Os was performed at the HI-13 tandem accelerator at the China Institute of Atomic Energy (CIAE). Lifetimes of excited states above 8+ in the yrast band in 178Os have been measured using the Doppler shift attenuation method. Lifetimes above 12+ states were measured for the first time. The deduced transitional quadruple moments (Qt), together with the previous data using the recoil distance Doppler shift (RDDS) method are compared with theoretical calculations based on the X(5) model and the interaction Boson model (IBM). Above the 10+ states, the Qt values fit well with the X(5) predictions. The present result suggests that the shape of a nucleus 178Os keeps X(5) critical point symmetry as spin increases to at .least 14+. The shape change of 178Os with spin increasing is similar to that of 176Os.%In order to investigate the evolution of X(5) in rotating 178Os,an experiment populating 178Os via the fusion evaporation reaction 154Sm(29Si,5n)178 Os was performed at the HI-13 tandem accelerator at the China Institute of Atomic Energy (CIAE).Lifetimes of excited states above 8+ in the yrast band in 178Os have been measured using the Doppler shift attenuation method.Lifetimes above 12+ states were measured for the first time.The deduced transitional quadruple moments (Qt ),together with the previous data using the recoil distance Doppler shift (RDDS) method are compared with theoretical calculations based on the X(5) model and the interaction Boson model (IBM).Above the 10+ states,the Qt values fit well with the X(5) predictions.The present result suggests that the shape of a nucleus 178Os keeps X(5) critical point symmetry as spin increases to at least 14+.The shape change of 178 Os with spin increasing is similar to that of 176 Os.Symmetry at critical points of deformation phase transition from a vibrator to an axial rotor

  9. Prácticas pedagógicas y competencias ciudadanas: El caso del docente de historia en Chile

    Directory of Open Access Journals (Sweden)

    Muñoz Labraña, Carlos

    2015-09-01

    Full Text Available En el presente artículo exponemos los resultados obtenidos sobre las prácticas pedagógicas y las competencias ciudadanas en una investigación financiada por el Centro de Investigación Avanzada en Educación (CIAE. En él analizamos algunas de las estructuras comunicativas presentes en la intervención didáctica del docente de Historia, Geografía y Ciencias Sociales de quinto a octavo año de Educación Básica en la ciudad de Concepción (Chile, desde donde se atiende la forma como estas interfieren en el desarrollo de determinadas competencias ciudadanas. Para ello, se utilizó una metodología cualitativa por medio de observaciones y registros de aula en 12 escuelas, tomando en consideración su dependencia administrativa. Los resultados demuestran cómo algunas de las dinámicas de comunicación y participación más comunes en las aulas dificultan y hasta contradicen el desarrollo de las competencias ciudadanas, que exigen el desarrollo autónomo y la participación activa de los estudiantes. Consecuentemente, el mundo de vivencias que conforman la realidad del aula resulta estar muy alejado de las experiencias propias de la vida social y democrática, donde idealmente los jóvenes debieran ser protagonistas para el desarrollo de una ciudadanía activa.

  10. Status and some safety philosophies of the China advanced research reactor CARR

    International Nuclear Information System (INIS)

    The existing two research reactors, HWRR (heavy water research reactor) and SPR (swimming pool reactor), have been operated by China Institute of Atomic Energy (CIAE) since, respectively, 1958 and 1964, and are both in extending service and facing the aging problem. It is expected that they will be out of service successively in the beginning decade of the 21st century. A new, high performance and multipurpose research reactor called China advanced research reactor (CARR) will replace these two reactors. This new reactor adopts the concept of inverse neutron trap compact core structure with light water as coolant and heavy water as the outer reflector. Its design goal is as follows: under the nuclear power of 60MW, the maximum unperturbed thermal neutron flux in peripheral D2O reflector not less than 8 x 1014 n/cm2. s while in central experimental channel, if the central cell to be replaced by an experimental channel, the corresponding value not less than 1 x 1015 n/cm2. s. The main applications for this research reactor will cover RI production, neutron scattering experiments, NAA and its applications, neutron photography, NTD for monocrystaline silicon and applications on reactor engineering technology. By the end of 1999, the preliminary design of CARR was completed, then the draft of preliminary safety analysis report (PSAR) was submitted to the relevant authority at the end of 2000 for being reviewed. Now, the CARR project has entered the detail design phase and safety reviewing procedure for obtaining the construction permit from the relevant licensing authority. This paper will only briefly introduce some aspects of safety philosophy of CARR design and PSAR. (orig.)

  11. Self-expandable stent loaded with 125I seeds: Feasibility and safety in a rabbit model

    International Nuclear Information System (INIS)

    Objective: To evaluate technical feasibility and acute and subacute radiotolerance of a self-expandable stent loaded with 125I seeds in the rabbit esophagus. Methods: A self-expandable stent designed for esophageal application was made of 0.16 mm nitinol wire and loaded with 125I seeds (CIAE-6711). Twenty-seven stents with three different radioactive dosages (n = 9 in each dosage group) were implanted in the esophagus of healthy rabbits, while nine stents alone were used as controls. The stents were perorally deployed into the esophagus under fluoroscopic guidance. Radiological follow-up included plain chest film, CT scan, and barium esophagography which were undertaken in all rabbits of each group at 2, 4, and 8 weeks, respectively, which were correlated to histopathological findings. The stented esophageal segments along with their adjacent tissues were harvested for histopathological examinations. Results: The stent was successfully deployed into the targeted esophageal segment in all rabbits. Neither 125I seeds dislodged from the stent during the deployment, nor they did during the follow-up period. The greatest (16.2 Gy) absorbed dose was found in the tissue 10 mm from 125I seeds at 8 weeks. Slight epithelial hyperplasia on the stent surface and submucosal inflammatory process developed at 2 weeks, which reached the peak at 8 weeks after the procedure. Significant thickness of the esophageal muscular layer was found at 8 weeks only in the groups with 125I seeds. On radiologic follow-up, moderate strictures on both ends of the stents developed at 4 weeks and became severe at 8 weeks after the procedure in all groups. Conclusion: Deployment of a self-expandable stent loaded with 125I seeds is technically feasible and safe within the first 8 weeks. Acute and subacute radiotolerance of the treated esophagus and its adjacent tissues by 125I seeds is well preserved in a healthy rabbit model

  12. Technical Research on Safety Management and Effective Application of China Advanced Research Reactor

    International Nuclear Information System (INIS)

    China Advanced Research Reactor (CARR) is a tank in pool type, light water cooled, heavy water reflected research reactor. The maximum thermal neutron flux of the reactor is 1.0x1015 cm-2s-1, and the reactor power is 60 MW. The reactor was designed and constructed completely by China Institute of Atomic Energy (CIAE). The construction project began on Aug. 26, 2002, reactor criticality was achieved on May 13, 2010, and it is scheduled to complete power increasing tests by the end of 2011. Future operation of CARR is preparing and its utilization program is considered. It is expected that CARR will greatly improve and enhance the comprehensive research capability of nuclear science and technology and push the peaceful use of nuclear technology forward. The paper briefly presents the reactor safety features, the operation organization and responsibilities, the management of operation safety, and the future utilizations. According to national safety regulations of research reactor, evaluation of operation safety of CARR shall be executed after initial operation at power level and submit the revised ''Final Safety Analysis Report'' (FSAR) to the regulatory body.Ordinary operation shall be approved and operation license shall be issued by the regulatory body after review on the ''Final Safety Analysis Report.'' Vertical and horizontal channels with associated equipment and instruments are installed in reactor core and in heavy water reflector. CARR will be used to produce variety of RIs in comprehensive fields, to meet the requirements of engineering tests and irradiation for developing NPP fuels and materials in China, to apply for NTD of mono-crystalline silicone, NAA, neutron photography and to provide high intense neutron beam for application of neutron scattering experiments in an adequate scale and others, etc. (author)

  13. High intensity proton beam transportation through fringe field of 70 MeV compact cyclotron to beam line targets

    Science.gov (United States)

    Zhang, Xu; Li, Ming; Wei, Sumin; Xing, Jiansheng; Hu, Yueming; Johnson, Richard R.; Piazza, Leandro; Ryjkov, Vladimir

    2016-06-01

    From the stripping points, the high intensity proton beam of a compact cyclotron travels through the fringe field area of the machine to the combination magnet. Starting from there the beams with various energy is transferred to the switching magnet for distribution to the beam line targets. In the design of the extraction and transport system for the compact proton cyclotron facilities, such as the 70 MeV in France and the 100 MeV in China, the space charge effect as the beam crosses the fringe field has not been previously considered; neither has the impact on transverse beam envelope coupled from the longitudinal direction. Those have been concerned much more with the higher beam-power because of the beam loss problem. In this paper, based on the mapping data of 70 MeV cyclotron including the fringe field by BEST Cyclotron Inc (BEST) and combination magnet field by China Institute of Atomic Energy (CIAE), the beam extraction and transport are investigated for the 70 MeV cyclotron used on the SPES project at Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro (INFN-LNL). The study includes the space charge effect and longitudinal and transverse coupling mentioned above, as well as the matching of beam optics using the beam line for medical isotope production as an example. In addition, the designs of the ±45° switching magnets and the 60° bending magnet for the extracted beam with the energy from 35 MeV to 70 MeV have been made. Parts of the construction and field measurements of those magnets have been done as well. The current result shows that, the design considers the complexity of the compact cyclotron extraction area and fits the requirements of the extraction and transport for high intensity proton beam, especially at mA intensity levels.

  14. Developing an Improved Heat Transfer Correlation for Applications in SCWR

    International Nuclear Information System (INIS)

    This thesis work seeks to complement ongoing research works on heat transfer from heated surface to supercritical water in the SCWR. The study was inspired by ongoing efforts directed at obtaining a correlation that predict supercritical-water heat transfer more accurately, especially with the identification of the SCWR concept as one of the six Generation IV nuclear reactors. The thesis focuses on the development of an improved heat transfer correlation for supercritical water flowing through a vertical heater in a natural circulation loop which is basically a bare vertical heater tube made of Inconnel-625, having an overall heating length of 1.37m and internal diameter of 4.62m. The study involves the investigation of some existing empirical heat transfer correlations for both forced and natural convections and then subsequently comparing their results to that of the Chen Yuzhou et al experimental dataset in order to notice their extent of deviations from the experimental data. Finally, one of the correlations considered for this study is used as a baseline to developing a more improved correlation. The parameters used for computing the selected heat transfer correlations and also developing an improved correlation are based on the wall and bulk temperatures obtained from the Supercritical-water heat-transfer dataset. The experiment for the dataset was performed in a natural circulation loop at the China Institute of Atomic Energy, China (CIAE) having pressure kept within the range of 24.2-25.2MPa, a heating power ranging from 0 to 18kW or heat flux from 0 to 0.91 MW/m2, and the maximum water temperature of up to 402 oC. A physical parametric sensitivity analysis was the technique used to develop and propose an improved Modified Churchill-Chu correlation with a reasonable agreement with the experimental data, having the least root mean square error of about 24% better than the investigated existing correlations. (au)

  15. The progress of researches on ADS in China

    International Nuclear Information System (INIS)

    The conceptual study of Accelerator Driven System (ADS) had lasted for about five years and ended in 1999 in China. As one project of 'the major state basic research program (973)' in energy domain, which is sponsored by the China Ministry of Science and Technology (MOST), a five years program of basic research for ADS physics and related technology has been launched since 2000. CIAE (China Institute of Atomic Energy), IHEP (Institute of High Energy Physics), PKU-IHIP (Institute of Heavy Ion Physics in Peking University) and other institutions are jointly carrying on the research. The research activities are focused on HPPA physics and technology, reactor physics of external source driven sub-critical assembly, nuclear data base and material study. For HPPA, a high current injector consisting of an ECR ion source, LEBT and a RFQ accelerating structure of 3MeV will be built. In reactor physics study, a series of neutron multiplication experimental study has been carried out and is being carrying on. The VENUS facility will be constructed as the basic experimental platform for the neutronic study in ADS blanket. It's a zero power sub-critical neutron multiplying assembly driven by external 14MeV neutron produced by a pulsed neutron genreator. The theoretical, experimental and simulation study on nuclear data, material properties and nuclear fuel circulation related to ADS is carrying on to provide the database for ADS system analysis. the experimental high current beam injector consisted of ECR ion source, low energy beam transport system and RFQ type acceleration structure. The injector is one of the most important part of the medium energy high power proton accelerator and of worldwide interest in this community. The main results on ADS related researches and primary physical consideration of this verification system--the Venus program will be reported. (authors)

  16. The 30 kW research reactor facility in Ghana: past, present and future programmes

    International Nuclear Information System (INIS)

    The Ghana Research Reactor-1 (GHARR-1) is a small, simple, reliable and safe reactor design and constructed by China Institute of Atomic Energy (CIAE). GHARR-1 adopts the pool-tank structure and employs highly enriched uranium as fuel, light water as moderator and coolant, metal beryllium as reflectors. The reactor is cooled by natural convention. The rated maximum thermal power of GHARR-1 is 30 kW; the corresponding neutron flux is 1.0x1012 cm-2s-1. The refueling mode of the reactor is to totally change the old core with a new one, the lifetime being more than ten years. Since the commencement of operation of the low-flux miniature neutron source reactor (MNSR) in 1995, a significant number of research and development in the field of neutron activation analysis have taken place. During its 12 years of operation, after the first criticality, the reactor has been used as a neutron source for research, teaching and training to support several graduate and post graduate careers for students from universities in Ghana and the West African sub-region. Owing to the stable flux of the reactor and rapid proliferation in utilization, several analytical techniques have been developed. The GHARR-1 application in neutron activation analysis included: (i) Food analysis; (ii) Heavy metals determination in environmental samples; (iii) Determination of major, minor and trace elements in geological samples; (iv) And mineral prospecting among others. The educational programmes in place at the center are teaching and learning in nuclear engineering, nuclear physics, nuclear and radiochemistry and other related fields. (author)

  17. Retrieval and Conditioning of High Level Radioactive Solid Waste From Pit-Type Storage Facilities%坑式废物库高水平放射性固体废物回取整备

    Institute of Scientific and Technical Information of China (English)

    张存平; 李美山; 纪永红; 初丽丽; 刘春秀; 叶国安

    2011-01-01

    A city radioactive waste temporary storage facility was operated for many years and aged seriously. In the 1970s, some high level radioactive solid waste (HLW) was stored in this facility because of bad management, which threatens the environment safety and should be retrieved and conditioned as soon as possible. According to the real condition in site, a retrieval technical process for HLW utilizing "robot-airproof work cell" was employed by the Department of Radioactive Waste Management, CIAE. The HLW was located in the No. 17 pit through contaminated level and detected hot-spot. After the mock-up test, the retrieval technical process was optimized. Finally, the HLW was successfully retrieved and conditioned in remote control way.%某核技术利用废库(城市废物库)超期服役,设备老化,20世纪70年代因管理不规范而收贮的高放固体废物给周围环境带来极大的安全隐患,需尽快妥善回取、处置.中国原子能科学研究院放射性三废设施治理工程部根据现场实际工况,设计制订了利用“机器人-气帐”系统回取高放废物的工艺路线.通过现场污染水平和库坑“热点”检测分析,查找到了17号库坑内高放固体废物的具体位置.通过回取实施前的模拟验证试验工作,优化了回取的技术路线.采用远距离回取技术,成功地实施了高放固体废物的回取和包装整备工作.

  18. The 30 kW research reactor facility in Ghana: Past, present and future programmes

    International Nuclear Information System (INIS)

    The Ghana Research Reactor-1 (GHARR-1) is a small, simple, reliable and safe reactor design and constructed by China Institute of Atomic Energy (CIAE). GHARR-1 adopts the pool-tank structure and employs highly enriched uranium as fuel, light water as moderator and coolant, metal beryllium as reflectors. The reactor is cooled by natural convention. The rated maximum thermal power of GHARR-1 is 30 kW; the corresponding neutron flux is 1.0x1012 cm-2s-1. The refueling mode of the reactor is to totally change the old core with a new one, the lifetime being more than ten years. Since the commencement of operation of the low-flux miniature neutron source reactor (MNSR) in 1995, a significant number of research and development in the field of neutron activation analysis have taken place. During its 12 years of operation, after the first criticality, the reactor has been used as a neutron source for research, teaching and training to support several graduate and post graduate careers for students from universities in Ghana and the West African sub-region. Owing to the stable flux of the reactor and rapid proliferation in utilization, several analytical techniques have been developed. As a national neutron source reactor facility, Ghana's MNSR also known as GHARR-1 is now successfully utilized in various areas of neutron activation analysis (NAA), teaching, research and training. The GHARR-1 application in neutron activation analysis included: (i) Food analysis; (ii) Heavy metals determination in environmental samples; (iii) Determination of major, minor and trace elements in geological samples; (iv) And mineral prospecting among others. The educational programmes in place at the center are teaching and learning in nuclear engineering, nuclear physics, nuclear and radiochemistry and other related fields. The paper will focus on the past and current status of GHARR-1 with respect to utilization and management and future programmes to enhance its uses in the fields of teaching

  19. Practices on nuclear security and international cooperation

    International Nuclear Information System (INIS)

    on Integrated Management of Nuclear Materials to introduce modern technology development on nuclear safeguards, material accounting and control, and physical protection in October 2005. After the Tech Demo, a series of cooperation projects on nuclear safeguards and security were developed. To support the security of 2008 Beijing Summer Olympic Games, China Atomic Energy Authority (CAEA), worked with IAEA and the U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA), carried out trainings for the officials from public security, border control and customs, etc. for strengthening the response capabilities to the Major Public Events (MPEs) and implemented physical security upgrades and radioactive sources recovery at facilities near Olympic venues. As a partner state of the Global Initiative to Combat Nuclear Terrorism, China organized a scenario-based workshop on radioactive detection and emergency response in cooperation with U.S. in December 2007, more than 60 Participants from 20 more countries participated the workshop. To strengthen the training capability on nuclear safeguards and security, CAEA and the IAEA jointly established a 'CAEA-IAEA Joint Training Center on Nuclear Safeguards and Security' in December 2006, located at China Institute of Atomic Energy (CIAE). International Cooperation is a very important element in developing global nuclear security regime. China is willing to make continuous efforts to promoting the development of nuclear security through international cooperation. (author)

  20. BN-600 hybrid core benchmark analyses (phases 1, 2 and 3) (draft synthesis report)

    International Nuclear Information System (INIS)

    UK, respectively), CIAE from China, IGCAR from India, JNC from Japan, KAERI from Rep. of Korea, IPPE and OKBM from the Russian Federation. The benchmark analyses consist of three Phases during 1999 - 2001 : RZ homogeneous benchmark (Phase 1), Hex-Z homogeneous benchmark (Phase 2), and Hex-Z heterogeneous and burnup benchmark (Phase 3). This report presents the results of benchmark analyses of a hybrid UOX/MOX fuelled core of the BN-600 reactor. The results for several relevant reactivity parameters obtained by the participants with their own state-of-the-art basic data and codes, were compared in terms of calculational uncertainty, and their effects on the ULOF transient behavior of the hybrid BN- 600 core were evaluated. Contributions of the participants in the benchmark analyses is shown. This report first addresses the benchmark definitions and specifications given for each Phase and briefly introduces the basic data, computer codes, and methodologies applied to the benchmark analyses by various participants. Then, the results obtained by the participants in terms of calculational uncertainty and their effect on the core transient behavior are intercompared. Finally it addresses some conclusions drawn in the benchmarks

  1. BN-600 fully MOX fuelled core benchmark analyses (phase 4) (draft synthesis report)

    International Nuclear Information System (INIS)

    design of that core. Basic principles of such core designs have been published elsewhere. The organizations participating in the BN-600 fully MOX fuelled core benchmark analyses are: ANL from the USA, CEA and SA from EU (France and the UK, respectively), CIAE from China, FZK/IKET from Germany, IGCAR from India, JNC from Japan, KAERI from the Republic of Korea, IPPE from the Russian Federation. For the specification of the Phase 4 benchmark, the following action was made: IPPE to provide a 3D Hex-Z MOX fuelled core model specification of BN- 600 with sodium plenum and post to the collaborators web site by the end of May 2002. Sufficient detail will be provided to allow the heterogeneous modelling of regions modelled heterogeneously in Phase 3 of the CRP (absorber rods, core fuel and axial blanket regions). This report first addresses the benchmark definitions and specifications given for Phase 4 and briefly introduces the basic data, computer codes, and methodologies applied to the benchmark analysis by various participants. Then, the results obtained by the participants in terms of calculational uncertainty and their effect on the core transient behavior are preliminary inter-compared

  2. BN-600 fully MOX fuelled core benchmark analyses (Phase 4). Draft synthesis report - Revision 1

    International Nuclear Information System (INIS)

    A benchmark analysis of a BN-600 fully mixed oxide (MOX) fuelled core design with sodium plenum above the core has been performed as an extension to the study of the BN-600 hybrid uranium oxide (UOX)/MOX fuelled core carried out during 1999-2001. This work was carried out within the the IAEA sponsored Co-ordinated Research Project (CRP) on 'Updated Codes and Methods to Reduce the Calculational Uncertainties of the LMFR Reactivity Effects'. This benchmark analysis retains the general objective of the CRP which is to validate, verify and improve methodologies and computer codes used for the calculation of reactivity coefficients in fast reactors aiming at enhancing the utilization of plutonium and minor actinides. The scope of the benchmark is to reduce the uncertainties of safety relevant reactor physics parameter calculations of MOX fuelled fast reactors and hence to validate and improve data and methods involved in such analyses. In previous benchmark analyses of the BN-600 hybrid core that closely conforms to a traditional configuration, the comparative analyses showed that sufficient accuracy is achieved using the diffusion theory approximation, widely applied in fast reactor physics calculations. With the purpose of investigating a core configuration of full MOX fuel loading, a core model of the BN-600 type reactor, designed to reduce the sodium void effect by installing a sodium plenum above the core, was newly defined for the next benchmark study. The specifications and input data for the benchmark neutronics calculations were prepared by EPPE (Russia). The specifications given for the benchmark describe only a preliminary core model variant and represent only one conceptual approach to BN-600 full MOX core designs. The organizations participating in the BN-600 fully MOX fuelled core benchmark analysis are: ANL from the USA, CEA and SA from EU (France and the UK, respectively), CIAE from China, FZK/IKET from Germany, IGCAR from India, JNC from Japan, KAERI

  3. Needs and Present Status of the First Multipurpose Nuclear Facilities in Jordan

    International Nuclear Information System (INIS)

    Full Text: Jordan is completely dependent on imports to cover its primary energy needs; about 98 percent of Jrodan's electricity generation is fuelled by imports of which about 70 percent is from Egyptian imported natural gas. The recent disruptions of the gas pipeline from Egypt highlight vividly this vulnerability and insecurity. Jordan is also one of the ten most water deprived countries in the world. The need of supply of water will increase in the coming decades, and desalination of water is one of the promising solutions to the water scarcity. However, water desalination is very energy intensive, and will further increase Jordan's need for electricity. Based on a pre-feasibility study conducted with the assistance of the IAEA, nuclear energy proved to be an important component of any future energy mix. Realizing the vital importance of human resource development, a nuclear engineering department was established in 2007 at Jordan University of Science and Technology (JUST). This past June witnessed the graduation of the first 19 engineers out of total of total 140 students in the department. They were trained in radiation detection and measurements laboratory and a virtual research reactor laboratory done via teleconference with the research reactor at North Carolina State University. To provide more practical experience for the students, Jordan Atomic Energy Commission (JAEC) launched two projects, a subcritical assembly and a research reactor, to be located at the campus of JUST. The Jordan Subcritical Assembly (JSA) project was contracted to China Institute of Atomic Energy (CIAE) in 2009. The facility has been built, constructed, and assembled. It is now ready for fuel loading and commissioning. The JSA has a of keff of 2 ceramic pellets of 3.4% U-235 in a Zr-4 cladding. These were assembled in a square lattice of 1.91 cm pitch and held between two perforated plates in a cylindrical tank filled with demineralized water. This JSA will witness the first