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Sub-Criticality Measurement with Source Term for Research Reactor in Inverse Kinetics Method 用逆动力学方法测量研究堆的源项亚临界度
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73011
N. Jahan, M. Rahman, M. Q. Huda, S. M. Seo
In reactor physics tests, it is important to monitor sub-criticality continuously during criticality approach. Reactivity measurements by the inverse kinetics method are widely used during the operation of a nuclear reactor. This technique is successfully applied at sufficiently high power level or to a core without an external neutron source where the neutron source term in point reactor kinetics equations may be neglected. For operation at low power levels or in the sub-critical domain, the increase in the fluctuation of the neutron signal may cause difficulties in the evaluation of reactivity and the effect of direct emission from the external neutron source may not be neglected. Therefore, contribution of the neutron source must be taken into account and this implies knowledge of a quantity proportional to the source strength, which calls the source term and then it should be determined. The research work has been conducted to measure reactivity with source term using a dedicated reactivity measurement system by the Least Square Inverse Kinetics Method (LSIKM). Application to a simulator of HANARO research reactor, Korea Atomic Energy Research Institute (KAERI), with known source strength and reactivity worth has showed consistent and satisfactory agreement.
在反应堆物理试验中,在临界进近过程中持续监测亚临界状态是很重要的。在核反应堆的运行过程中,反动力学方法的反应性测量被广泛使用。该技术在足够高的功率水平下或在没有外部中子源的堆芯上成功应用,其中点反应堆动力学方程中的中子源项可以忽略。对于低功率水平或亚临界域的运行,中子信号波动的增加可能会导致反应性评估的困难,并且外部中子源直接发射的影响不能被忽视。因此,必须考虑中子源的贡献,这意味着知道一个与源强度成比例的量,它称为源项,然后应该确定它。研究工作是通过最小二乘逆动力学方法(LSIKM)使用专用反应性测量系统测量源项的反应性。在已知源强度和反应性价值的HANARO研究堆模拟器韩国原子能研究所(KAERI)上的应用显示出一致和令人满意的一致性。
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引用次数: 1
Determination of Uranium Traces in Nuclear Reactor IEA-R1 Pool Water 核反应堆iaea - r1池水中痕量铀的测定
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73014
A. M. Saliba-Silva, O. D. Santos, E. U. Carvalho, H. Riella, M. Durazzo
IEA-R1 nuclear reactor operation has the routine to control uranium content in pool water to be in trace range below 50 μg/L. There are several routes to determine the uranium trace content in water in the literature; voltammetry has been systematically employed. In the present study, the chosen chemical determination of uranium traces used the voltammetric method known as AdCSV (adsorptive cathodic stripping voltammetry). This technique, based on mercury voltammetry, is an adequate methodology to determine uranium traces. The chloranilic acid [CAA] (2,5-dichloro-3,6-dihydroxy-1,4-benzo-quinone) is indicated as chelating agent. The redox reaction of UO2+2 with CAA is sensitive in the range of 2 2(CAA)2] reduction potential. In this work, we present the uranium trace results for IEA-R1 reactor water, sampled after an operation routine shutdown. The uranium trace determination for IEA-R1 pool water showed content around 1 μg/L [U] with statistical significance. Therefore the IEA-R1-reactor-water purification showed to be adequate and safe.
IEA-R1核反应堆的常规操作是将池水中的铀含量控制在50μg/L以下。文献中有几种测定水中痕量铀含量的方法;伏安法已被系统地应用。在本研究中,所选择的痕量铀的化学测定使用了被称为AdCSV(吸附阴极溶出伏安法)的伏安法。这种基于汞伏安法的技术是测定痕量铀的适当方法。氯苯胺酸[CAA](2,5-二氯-3,6-二羟基-1,4-苯醌)被认为是螯合剂。UO2+2与CAA的氧化还原反应在2 2(CAA)2]还原电位范围内是敏感的。在这项工作中,我们介绍了IEA-R1反应堆水的铀示踪结果,这些结果是在操作常规停堆后采样的。IEA-R1池水的铀痕量测定显示含量约为1μg/L[U],具有统计学意义。因此,IEA-R1-反应物-水的纯化被证明是充分和安全的。
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引用次数: 3
Response of COX2/PGE2 Inflammatory Pathway to Brown Seaweed Extract in Rats Exposed to Gamma Radiation COX2/PGE2炎症通路对γ射线照射大鼠褐藻提取物的反应
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73016
K. Azab, N. Meky, Eglal A. M. El-Deghidy, Ghada Azoz
Background: Systemic inflammation due to radiation exposure has been identified in a biological system by certain metabolic and behavioral disorders. These anarchies mostly mediated under a regulation of cyclooxygenase 2 (COX2) induced production of an inflammatory mediator prostaglandin E2 (PGE2). Aim: This study was undertaken to investigate the anti-inflammatory impact of brown sea weed extract (BSWE) against induction of COX2/PGE2 inflammatory pathway in gamma-irradiated rats. Rats were orally administrated with BSWE (27 mg/kg body weight/day) for 7 consecutive days before exposure to 8 Gy fractionated gamma radiation (2 Gy × 4; every 3 days). Treatment with BSWE was extended along with and in-between irradiation doses for another 14 successive days. Our data demonstrated that the administration of BSWE to rats exposed to gamma radiation, following the regimen suggested, significantly neutralize the changes induced in the inflammatory molecules COX2, PGE2, tumor necrosis alpha (TNF-α), and nitric oxide (NO). In addition, it adjusted significantly the cellular redox tone via regulation of changes induced in malondialdehyde (MDA) reduced glutathione (GSH), superoxide dismutase (SOD) catalase (CAT) and xanthine oxidoreductase system (XOR). Credibly, from the results emerged in this study, it could be suggested that BSWE has substantial anti-inflammatory activities and gamma radiation protection capabilities. It is recommended to include BSWE in the treatment strategy of various inflammatory diseases especially cancer as a safe natural anti-inflammatory agent.
背景:辐射暴露引起的全身性炎症在生物系统中已被确定为某些代谢和行为障碍。这些无政府状态主要是在环氧化酶2 (COX2)诱导炎症介质前列腺素E2 (PGE2)产生的调节下介导的。目的:研究褐海草提取物(BSWE)对γ辐照大鼠COX2/PGE2炎症通路的抗炎作用。大鼠连续7天口服BSWE (27 mg/kg体重/天),然后暴露于8 Gy分次γ辐射(2 Gy × 4;每3天)。BSWE治疗随辐照剂量和中间剂量延长,再连续14天。我们的数据表明,按照建议的方案,给暴露于伽马辐射的大鼠服用BSWE,可以显著中和炎症分子COX2、PGE2、肿瘤坏死α (TNF-α)和一氧化氮(NO)的变化。此外,它还通过调节丙二醛(MDA)还原谷胱甘肽(GSH)、超氧化物歧化酶(SOD)过氧化氢酶(CAT)和黄嘌呤氧化还原酶系统(XOR)的变化,显著调节细胞氧化还原张力。可信的是,从本研究的结果可以看出,BSWE具有实质性的抗炎活性和γ辐射防护能力。建议将BSWE作为一种安全的天然抗炎剂纳入各种炎症性疾病特别是癌症的治疗策略中。
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引用次数: 6
Geometric Models of Atomic Nuclei 原子核的几何模型
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73017
G. Bihari
While experimenting with the more and more popular neodymium magnetic ball sets, the author developed a method, by which models of atomic nuclei can be created. These macroscopic models visually represent several features of nuclei and nuclear phenomena, which can be a useful mean during the teaching of nuclear physics. Even though such macroscopic models are unable to depict the true quantum physical nature of nuclear processes, they can be much more useful didactically than the previously used disordered sets of balls, to represent the atomic nucleus.
在对越来越流行的钕磁球组进行实验的过程中,作者提出了一种建立原子核模型的方法。这些宏观模型直观地反映了原子核和核现象的若干特征,在核物理教学中是一种有用的手段。尽管这种宏观模型无法描述原子核过程的真正量子物理性质,但它们在教学上比以前使用的无序球组更有用,可以代表原子核。
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引用次数: 1
The role of nuclear power from a system engineering standpoint 从系统工程的角度来看核能的作用
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73015
L. O. Freire, D. A. Andrade
This work proposed the application of system engineering methods to identify organizations vital for society, seeking development and well-being. System engineering requires the identification of blocks (or systems), identification of their service functions, identification of states, identification of required quality and identification of constraints. Analyzing modern societies, vital functions were identified and countries behavior was modeled, identifying their states. In this context, nuclear power was found to be fundamental for development and defense because of its inherent advantages for military naval purposes at war. Another striking conclusion is that nuclear power is the best solution for country energy security, more than to avoid climate changes, but to help the nation to resist climate changes. A solution to mitigate the high overnight costs of nuclear power was also proposed. It was demonstrated qualitatively that the adoption of dual purpose mobile nuclear power plants military performances, economic development and risks management.
这项工作提出了应用系统工程方法来识别对社会至关重要、寻求发展和福祉的组织。系统工程需要识别块(或系统)、识别其服务功能、识别状态、识别所需质量和识别约束。通过分析现代社会,确定了重要功能,并对国家行为进行了建模,确定了其状态。在这种情况下,核能被认为是发展和防御的基础,因为它在战争中具有海军军事用途的固有优势。另一个引人注目的结论是,核能是国家能源安全的最佳解决方案,不仅仅是为了避免气候变化,而是为了帮助国家抵御气候变化。还提出了一种解决方案,以减轻核能的高昂夜间成本。定性地证明了采用两用移动核电站的军事性能、经济发展和风险管理。
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引用次数: 5
Gamma Radiation Measurements of Naturally Occurring Radioactive in Igneous Rocks and Its Radiological Complications 火成岩中天然放射性物质的伽马辐射测量及其放射并发症
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73012
J. Al-Zahrani
The concentrations of natural radioactivity were measured in igneous rock samples collected from Albaha region in the south west of Saudi Arabia. A high purity germanium (HPGe) detector was used for analysis. The average activity concentrations for 226Ra, 232Th and 40K were 35, 31.52 and 843.63 Bq kg−1, respectively. The average absorbed dose rate was 70.86 nGy⋅h−1 with a corresponding average annual effective dose 0.09 mSv⋅y−1. The average radium equivalent activity value was 145.84 Bq⋅kg−1, lower than the international limit 370 Bq⋅kg−1. The external and internal indices average values were 0.39 and 0.49, respectively. The average results obtained in this study are lower than the average national and world recommended values, therefore, there is no health risk to the populace of the area. This study provides a baseline map of background radioactivity levels in the Saudi environment and will be used as reference information to assess any changes in the level background due to geological processes.
对采集自沙特阿拉伯西南部Albaha地区的火成岩样品进行了天然放射性浓度测量。采用高纯锗(HPGe)检测器进行分析。226Ra、232Th和40K的平均活性浓度分别为35、31.52和843.63 Bq kg−1。平均吸收剂量率为70.86 nGy⋅h−1,相应的年平均有效剂量为0.09 mSv⋅y−1。平均镭当量活度值为145.84 Bq⋅kg−1,低于国际标准370 Bq⋅kg−1。外部指标平均值为0.39,内部指标平均值为0.49。本研究获得的平均结果低于国家和世界的平均推荐值,因此,对该地区的民众没有健康风险。这项研究提供了沙特阿拉伯环境中本底放射性水平的基线图,并将作为参考资料,用于评估由于地质作用而引起的本底放射性水平的任何变化。
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引用次数: 4
Neutron Flux Signal Acquisition from Plant Instrumentation Channel of Research Reactor for Reactivity Calculation 用于反应性计算的研究堆装置仪表通道中子通量信号采集
Pub Date : 2017-06-15 DOI: 10.4236/WJNST.2017.73013
N. Jahan, M. Rahman, M. Q. Huda
A design for instantaneous neutron flux signal acquisition system is being carried out for reactivity measurement of the nuclear research reactor. It is a computer-based digital data acquisition system that can perform continuous monitor and measurement of reactivity inserted into or removed from the research reactor. The acquisition system accomplishes with two major parts. The first part is an interfacing PCI based data acquisition card and the corresponding driver software intending to on-line acquisition of neutron flux signals from plant instrumentation channel. The second part incorporates the high-level Visual Basic real time program, indigenously developed for computation of reactivity by the solution of neutron point kinetic equations and other relevant functional modules like input file logging, reactivity calculation, graphics demonstration etc.
研究了一种用于核研究堆反应性测量的瞬时中子通量信号采集系统的设计。它是一种基于计算机的数字数据采集系统,可以对研究堆插入或取出的反应性进行连续监测和测量。采集系统由两大部分来实现。第一部分是基于PCI接口的数据采集卡和相应的驱动软件,用于在线采集工厂仪表通道的中子通量信号。第二部分采用了我国自主开发的利用中子动力学方程求解反应性计算的高级Visual Basic实时程序,以及输入文件记录、反应性计算、图形演示等相关功能模块。
{"title":"Neutron Flux Signal Acquisition from Plant Instrumentation Channel of Research Reactor for Reactivity Calculation","authors":"N. Jahan, M. Rahman, M. Q. Huda","doi":"10.4236/WJNST.2017.73013","DOIUrl":"https://doi.org/10.4236/WJNST.2017.73013","url":null,"abstract":"A design for instantaneous neutron flux signal acquisition system is being carried out for reactivity measurement of the nuclear research reactor. It is a computer-based digital data acquisition system that can perform continuous monitor and measurement of reactivity inserted into or removed from the research reactor. The acquisition system accomplishes with two major parts. The first part is an interfacing PCI based data acquisition card and the corresponding driver software intending to on-line acquisition of neutron flux signals from plant instrumentation channel. The second part incorporates the high-level Visual Basic real time program, indigenously developed for computation of reactivity by the solution of neutron point kinetic equations and other relevant functional modules like input file logging, reactivity calculation, graphics demonstration etc.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-06-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"41796862","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
Coupling a Gas Chromatography Unit to an Inductively Coupled Plasma Mass Spectrometer 气相色谱装置与电感耦合等离子体质谱仪的耦合
Pub Date : 2017-04-03 DOI: 10.4236/WJNST.2017.72007
Jerrad P. Auxier, J. Auxier, H. Hall
Although the eminent threat of a terrorist group detonating an improvised nuclear device (IND) in an urban environment is low, it is crucial that countries develop modern nuclear forensic capabilities to expedite response in a post-detonation scenario. In particular, new instruments need to be created to shorten dissolution time, expedite chemical separation, and improve forensic analysis of the nuclear melt glass that is created during the detonation of the device. To expedite this process, an instrument was designed to thermally couple a gas chromatograph (GC) to a time-of-flight inductively coupled plasma time-of-flight mass spectrometer (ICPTOFMS) In order to couple these two instruments, another instrument was designed to provide an isothermal atmosphere between the GC and TOFICPMS to expedite rapid gas separations processes. By using gas separations instead of the current wet chemistry processes, the required separation and analysis time of the melt glass significantly decreases. The new instrument would also provide a more detailed analysis of the elemental and isotopic composition of the melt glass. By completing these tasks simultaneously, this significantly decreases the required time to conduct these separations and improves the elemental and isotopic analysis.
尽管恐怖组织在城市环境中引爆简易核装置的显著威胁很低,但各国必须发展现代核取证能力,以加快在爆炸后情况下的反应。特别是,需要制造新的仪器,以缩短溶解时间,加快化学分离,并改进对装置爆炸过程中产生的核熔融玻璃的法医分析。为了加快这一过程,设计了一种仪器将气相色谱仪(GC)与飞行时间电感耦合等离子体飞行时间质谱仪(ICPTOFMS)热耦合。为了耦合这两种仪器,设计了另一种仪器在气相色谱仪和TOFICPMS之间提供等温气氛,以加快快速气体分离过程。通过使用气体分离代替目前的湿法化学工艺,熔融玻璃所需的分离和分析时间显著减少。新仪器还将对熔融玻璃的元素和同位素组成进行更详细的分析。通过同时完成这些任务,这大大减少了进行这些分离所需的时间,并改进了元素和同位素分析。
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引用次数: 1
On-Site Calibration Method of Dosimeter Based on X-Ray Source 基于x射线源的剂量计现场标定方法
Pub Date : 2017-04-03 DOI: 10.4236/WJNST.2017.72008
Wenhui Lv, Huiping Guo, N. Lv, Chenyang Tian, K. Zhao, Xiaotian Wang, Yijie Hou
The real-time monitoring of environmental radiation dose for nuclear fa-cilities is an important part of safety, in order to guarantee the accuracy of the monitoring results regular calibration is necessary. Around nuclear facilities there are so many environmental dosimeters installed dispers-edly, because of its huge quantity, widely distributed, and in real-time monitoring state; it will cost lots of manpower and finance if it were tak-en to calibrate on standard laboratory; what’s more it will make the en-vironment out of control. To solve the problem of the measurement ac-curacy of the stationary gamma radiation dosimeter, an on-site calibra-tion method is proposed. The radioactive source is X-ray spectrum, and the dose reference instrument which has been calibrated by the national standard laboratory is a high pressure ionization. On-site calibration is divided into two parts; firstly the energy response experiment of dosim-eter for high and low energy is done in the laboratory, and the energy response curve is obtained combining with Monte Carlo simulation; sec-ondly experiment is carried out in the field of the measuring dosimeter, and the substitution method to calibrate the dosimeter is used; finally the calibration coefficient is gotten through energy curve correction. In order to verify the accuracy of on-site calibration method, the calibrated dosimeter is test in the standard laboratory and the error is 3.4%. The re-sult shows that the on-site calibration method using X-ray is feasible, and it can improves the accuracy of the measurement results of the stationary γ-ray instrument; what’s more important is that it has great reference value for the radiation safety management and radiation environment evaluation.
核设施环境辐射剂量实时监测是核设施安全的重要组成部分,为了保证监测结果的准确性,需要对监测结果进行定期校准。核设施周边环境剂量计安装分散,数量庞大,分布广泛,处于实时监测状态;如果在标准实验室进行校准,将耗费大量人力和财力;更重要的是,它会使环境失控。针对固定式伽玛辐射剂量计测量精度问题,提出了一种现场校准方法。放射源为x射线谱,剂量参考仪为高压电离,经国家标准实验室标定。现场校准分为两个部分;首先在实验室进行了高、低能量剂量计的能量响应实验,并结合蒙特卡罗模拟得到了能量响应曲线;其次,在测量剂量计的现场进行了实验,并采用代入法对剂量计进行了标定;最后通过能量曲线校正得到标定系数。为了验证现场校准方法的准确性,校准后的剂量计在标准实验室进行了测试,误差为3.4%。结果表明,采用x射线现场标定方法是可行的,可以提高固定式γ射线仪测量结果的精度;更重要的是对辐射安全管理和辐射环境评价具有重要的参考价值。
{"title":"On-Site Calibration Method of Dosimeter Based on X-Ray Source","authors":"Wenhui Lv, Huiping Guo, N. Lv, Chenyang Tian, K. Zhao, Xiaotian Wang, Yijie Hou","doi":"10.4236/WJNST.2017.72008","DOIUrl":"https://doi.org/10.4236/WJNST.2017.72008","url":null,"abstract":"The real-time monitoring of environmental radiation dose for nuclear fa-cilities is an important part of safety, in order to guarantee the accuracy of the monitoring results regular calibration is necessary. Around nuclear facilities there are so many environmental dosimeters installed dispers-edly, because of its huge quantity, widely distributed, and in real-time monitoring state; it will cost lots of manpower and finance if it were tak-en to calibrate on standard laboratory; what’s more it will make the en-vironment out of control. To solve the problem of the measurement ac-curacy of the stationary gamma radiation dosimeter, an on-site calibra-tion method is proposed. The radioactive source is X-ray spectrum, and the dose reference instrument which has been calibrated by the national standard laboratory is a high pressure ionization. On-site calibration is divided into two parts; firstly the energy response experiment of dosim-eter for high and low energy is done in the laboratory, and the energy response curve is obtained combining with Monte Carlo simulation; sec-ondly experiment is carried out in the field of the measuring dosimeter, and the substitution method to calibrate the dosimeter is used; finally the calibration coefficient is gotten through energy curve correction. In order to verify the accuracy of on-site calibration method, the calibrated dosimeter is test in the standard laboratory and the error is 3.4%. The re-sult shows that the on-site calibration method using X-ray is feasible, and it can improves the accuracy of the measurement results of the stationary γ-ray instrument; what’s more important is that it has great reference value for the radiation safety management and radiation environment evaluation.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"46462595","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Numerical Analysis for Transients in External Source Driven Reactors 外部源驱动反应堆瞬态的数值分析
Pub Date : 2017-04-03 DOI: 10.4236/WJNST.2017.72009
Willian Vieira de Abreu, A. Gonçalves, Z. R. Lima
The main purpose of this paper is to perform a numerical analysis of the Neutron Spatial Kinetic Equations, subject to transients of the External Neutron Source, by applying the Implicit Euler Method as well as the Runge-Kutta Method in order to check which methods are best applicable in transients caused by External Neutron Source. For this purpose, a one-dimensional ADS reactor with a constant external source was simulated based on the geometry of ANL-BSS-6 reactor for benchmark effects.
本文的主要目的是通过应用隐式欧拉方法和龙格-库塔方法,对外部中子源瞬态下的中子空间动力学方程进行数值分析,以检查哪些方法最适用于外部中子源引起的瞬态。为此,基于ANL-BSS-6反应堆的几何结构,对具有恒定外部源的一维ADS反应堆进行了基准效应模拟。
{"title":"Numerical Analysis for Transients in External Source Driven Reactors","authors":"Willian Vieira de Abreu, A. Gonçalves, Z. R. Lima","doi":"10.4236/WJNST.2017.72009","DOIUrl":"https://doi.org/10.4236/WJNST.2017.72009","url":null,"abstract":"The main purpose of this paper is to perform a numerical analysis of the Neutron Spatial Kinetic Equations, subject to transients of the External Neutron Source, by applying the Implicit Euler Method as well as the Runge-Kutta Method in order to check which methods are best applicable in transients caused by External Neutron Source. For this purpose, a one-dimensional ADS reactor with a constant external source was simulated based on the geometry of ANL-BSS-6 reactor for benchmark effects.","PeriodicalId":61566,"journal":{"name":"核科学与技术国际期刊(英文)","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2017-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"43119644","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 1
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