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.


Baiocco G.,Nuclear and Industrial Engineering NINE | Petruzzi A.,Nuclear and Industrial Engineering NINE | Bznuni S.,Nuclear and Radiation Safety Center | Kozlowski T.,Urbana University
Annals of Nuclear Energy | Year: 2017

Lattice physics codes are primarily used to generate cross-section data for nodal codes. In this work the methodology of homogenized constant generation was applied to a small Pressurized Water Reactor (PWR) core, using the deterministic code Helios and the Monte Carlo code Serpent. Subsequently, a 3D analysis of the PWR core was performed with the nodal diffusion code PARCS using the two-group cross section data sets generated by Helios and Serpent. Moreover, a full 3D model of the PWR core was developed using Serpent in order to obtain a reference solution. Several parameters, such as keff, axial and radial power, fission and capture rates were compared and found to be in good agreement. © 2017 Elsevier Ltd


Liu Q.-F.,Nuclear and Radiation Safety Center | Han J.-R.,Nuclear and Radiation Safety Center | Han X.-Z.,Nuclear and Radiation Safety Center | Lv C.-X.,Nuclear and Radiation Safety Center | Zhang C.-M.,Nuclear and Radiation Safety Center
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2016

The relative concentrations are major parameters for control room habitability assessments. ARCON96 computer code is developed for U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation for control room habitability assessments. The fundamental and the main theoretical models are analyzed. As a building surface release modeling, a sensitivity analysis on relative concentrations of a nuclear power plant containment radiological release is carried out. Some suggestions which would make the calculation more scientific are provided. © 2016, Editorial Board of Nuclear Electronics & Detection Tech. All right reserved.


Hu W.,Nuclear and Radiation Safety Center | Hu W.,North China Electrical Power University | Jing J.,Nuclear and Radiation Safety Center | Bi J.,Nuclear and Radiation Safety Center | And 3 more authors.
Annals of Nuclear Energy | Year: 2017

Minor actinides are the primary contributors to long term radiotoxicity in spent fuel. The majority of commercial reactors in operation in the world are PWRs, so to study the minor actinide transmutation characteristics in the PWRs and ultimately realize the successful minor actinide transmutation in PWRs are crucial problem in the area of the nuclear waste disposal. The key issues associated with the minor actinide transmutation are the appropriate loading patterns when introducing minor actinides to the PWR core. We study two different minor actinide transmutation materials loading patterns on the PWR burnable poison rods, one is coating a thin layer of minor actinide in the water gap between the zircaloy cladding and the stainless steel which is filled with water, another one is that minor actinides substitute for burnable poison directly within burnable poison rods. Through considering the loading patterns, loading amount and self-shielding effect and so on, when the outer diameter of MA is 0.520 cm, the transmutation rate of MA is 38.5%, it is the optimal configuration, firstly transmutation rate and loading amount of MA with the pattern of MA in the water gap of burnable poison rods are larger than ones with the pattern of MA substitute for part burnable poison. Secondly the highest transmutation rate means the least loading amount of MA and the lowest transmutation rate means the most loading amount of MA. In order to keep reasonable transmutation rate and loading amount, when the outer diameter of MA is 0.520 cm, it would not reduce dramatically the amount of MA and the MA loading of this loading pattern is equivalent to the discharge amount of five pressurized water reactor, at the same time, the transmutation rate can keep reasonable level. © 2017


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.


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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