Nuclear and Radiation Safety Center

Beijing, China

Nuclear and Radiation Safety Center

Beijing, China

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Gao Y.,China Nuclear Power Engineering Co. | Li L.,Nuclear and Radiation Safety Center | Ma Y.-W.,China Nuclear Power Engineering Co. | Fan J.,China Nuclear Power Engineering Co.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2016

The paper expounds panel seismic qualification methodology based on finite element model (FEM) validation. Through the specimen seismic qualification test and FEM validation analysis, it integrates the panel structure design and finite element analysis. In addition, it introduces correct factor during panel FEM validation analysis to ensure the seismic resistance performance of control room panels with a proper safety margin. © 2016, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.


Qi Y.,Nuclear and Radiation Safety Center | Zhang W.,Nuclear and Radiation Safety Center | Zhang Q.-E.,Nuclear and Radiation Safety Center | Yang L.-L.,Nuclear and Radiation Safety Center
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2016

Several anomalies of flashing high counting rate in ex-core neutron instrumentation system occurred recently in some new nuclear power plants in China. As reasons of these anomalies, the cable connector problems and detector failure problems are analyzed from aspects of fault phenomenon, cause examination, and solutions. Concerns on the manufacture and installation of ex-core neutron instrumentation equipment should be raised by nuclear power plants. This paper can be used for reference on solution and avoiding similar issues for other nuclear power plants. © 2016, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.


Shi S.,PLA Second Artillery Engineering University | Ma W.-Y.,PLA Second Artillery Engineering University | Yang Y.-F.,Nuclear and Radiation Safety Center | Wang J.-H.,PLA Second Artillery Engineering University | And 2 more authors.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2014

Image reconstruction algorithm is an important part in muon tomography imaging techniques. This paper introduced the basic principle of cosmic ray muon tomography based on multiple Coulomb scattering, studied the principle and method of muon tomography imaging algorithm. With the comparison of the imaging results, this paper analyzed the characteristics of various algorithms, summarized the advantages and disadvantages of different algorithm in imaging precision and operation speed, and explored the future developing trend of muon tomography imaging algorithms. ©, 2014, Atomic Energy Press. All right reserved.


Poghosyan S.,Nuclear and Radiation Safety Center | Malkhasyan A.,Nuclear and Radiation Safety Center | Rodionov A.,Institute for Energy and Transport of the Netherlands | Rodionov A.,Institute for Radiological Protection and Nuclear Safety
10th International Conference on Probabilistic Safety Assessment and Management 2010, PSAM 2010 | Year: 2010

The paper presents the results of a case study on "VVER-440 component age-dependent reliability data assessment" performed in the frame of European Commission Joint Research Center (EC JRC) Ageing PSA (APSA) Network activities. The study is aimed to demonstrate the feasibility to apply the methods and approaches developed within APSA Network for assessment of ageing trends and elaboration of time-dependent reliability models for the case of VVER-440 generic component reliability data. These approaches are presented in the special data analysis guideline produced within APSA Network. The Guidelines mostly oriented to active safety components supposing that the reliability data are collected for the large statistical samples during the long period of time. The conditions regarding the sample size and duration of data collection period are very difficult to satisfy in case of only one plant-specific data collection. This is the case of VVER-440 reactors operated in Europe. For all of them the reliability data were collected in the frame of PSA development on the plant specific basis. The case study treats the statistical data provided by APSA Network participants for three components types: diesel generators, main feedwater pumps and 6.0kV breakers. The results of the study discuss the pulling procedure and time-dependent models construction.


Zhang Y.X.,Nuclear 404 Ltd Company | Wang C.Z.,Nuclear and Radiation Safety Center | Zhang Y.L.,Hanshan Normal University | Li Z.W.,Hanshan Normal University
Advanced Materials Research | Year: 2014

CuO/ã-Al2O3 catalyst was used to deal with the waste leachate in CWAO technology of, and the SEM and TEM characterization showed: active component in the surface of the carrier distribution is uniform; In CWAO process, six factors, based on the CODCr removal rate and turbidity removal rate, the biggest impact factor is reaction temperature, and the influence factors of the top three were reaction temperature, catalyst dosage and reaction time. The influence factors of those in the bottom three are influent water pH, oxygen partial pressure, stirring intensity, and three factors of influence on the strength is close. Optimizing operation process, in order: reaction temperature of 200 °C, catalyst dosage of 1.5 g, oxygen partial pressure of 2.0 MPa, stirring intensity 800 rpm, influent water pH of 7.0, the reaction time of 70 min. © (2014) Trans Tech Publications, Switzerland.


Chen J.,National Key Laboratory of Science and Technology on Reactor System Design Technology | Li L.,Nuclear and Radiation Safety Center | Fan J.,China Nuclear Power Engineering Co. | Liu H.-C.,National Key Laboratory of Science and Technology on Reactor System Design Technology
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2015

In order to guarantee the quality and reliability of instrumentation and control equipment of nuclear power plant, the quality control of the electronic components should be strengthened. This paper analyzes the problems of the component quality control of I&C equipment of nuclear power plant, puts forward some key points that should be paid attention to in the application of the electronic components, focuses on the quality grade of components, The component secondary screening and other aspects, provides reference for the localization of I&C equipment of nuclear power plant. © 2015, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.


Zhao D.-L.,Xi'an Jiaotong University | Wu Y.-L.,Xi'an Jiaotong University | Zhang B.-P.,Xi'an Jiaotong University | Zhang B.-P.,Nuclear and Radiation Safety Center
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2011

It introduces the key component CCD in the radiation imaging system's: the radiation test assessment method, the layout of the laboratory equipments as well as the changes of the CCDs imaging capacity before and after irradiation. The main performance, the CCD gray value V.S. the irradiated time, was monitored on-line. access to the CCD in its radiation performance of the work environment changes over time. The preliminary conclusions on the CCDs anti-radiation performance were obtained and discussed.


Ma C.-W.,Henan Normal University | Lv C.-J.,Henan Normal University | Zhang G.-Q.,CAS Shanghai Institute of Applied Physics | Wang H.-W.,CAS Shanghai Institute of Applied Physics | Zuo J.-X.,Nuclear and Radiation Safety Center
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms | Year: 2015

Neutron-induced reactions on 27Al and 19F nuclei are investigated using the optical model implemented in the TALYS 1.4 toolkit. Incident neutron energies in a wide range from 0.1 keV to 30 MeV are calculated. The cross sections for the main channels (n, np), (n, p), (n, α), (n, 2n), and (n, γ) and the total reaction cross section (n, tot) of the reactions are obtained. When the default parameters in TALYS 1.4 are adopted, the calculated results agree with the measured results. Based on the calculated results for the n + 27Al and n + 19F reactions, the results of the n + 27Al19F reactions are predicted. These results are useful both for the design of thorium-based molten salt reactors and for neutron activation analysis techniques. © 2015 Elsevier B.V.


Lu C.-J.,Henan Normal University | Ma C.-W.,Henan Normal University | Liu Y.-P.,Henan Normal University | Zhang W.-G.,Henan Normal University | Zuo J.-X.,Nuclear and Radiation Safety Center
Nuclear Science and Techniques | Year: 2015

In radiotherapy, the energy of the γ rays used could be larger than 10 MeV, which would potentially activate stable nucleus into a radioactive one. The γ induced reactions on some of the human essential elements are studied to show the probability of changes of nuclei. The Talys 1.4 toolkit was adopted as the theoretical model for calculation. The reactions investigated include the (γ, n) and (γ, p) channels for the stable Na, Mg, Cl, K, Ca, and Fe isotopes, with the incident energy of γ ranging from 1 to 30 MeV. It was found that the cross sections for the reactions are very low, and the maximum cross section is no larger than 100 mb. By considering the threshold energy of the channel, the half-life time of the residue nucleus, and the percentage of the element accounting for the weight and its importance in the body, it is suggested to track the radioactive nuclei 22Na, 41Ca, and 42,43 K after γ therapy. The results might be useful for medical diagnosis and disease treatment. © 2015, Science Press. All rights reserved.


Sadiq M.,Center for Nuclear Safety | Xiu Yun Z.,Nuclear and Radiation Safety Center | Rong P.,Nuclear and Radiation Safety Center
Nuclear Engineering and Design | Year: 2014

The steel plate reinforced concrete and reinforced concrete structures are used in nuclear power plants for protection against impact of an aircraft. In order to compare the impact resistance performance of steel plate reinforced concrete and reinforced concrete slabs panels, simulation analysis of 1/7.5 scale model impact tests is carried out by using finite element code ANSYS/LS-DYNA. The damage modes of all finite element models, velocity time history curves of the aircraft engine and damage to aircraft model are compared with the impact test results of steel plate reinforced concrete and reinforced concrete slab panels. The results indicate that finite element simulation results correlate well with the experimental results especially for constitutive winfrith concrete model. Also, the impact resistance performance of steel plate reinforced concrete slab panels is better than reinforced concrete slab panels, particularly the rear face steel plate is very effective in preventing the perforation and scabbing of concrete than conventional reinforced concrete structures. In this way, the thickness of steel plate reinforced concrete structures can be reduced in important structures like nuclear power plants against impact of aircraft. It also demonstrates the methodology to validate the analysis procedure with experimental and analytical studies. It may be effectively employed to predict the precise response of safety related structures against aircraft impact. © 2014 Elsevier B.V.

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