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The MADERE Radio-activity Measurement Platform: Developments for a Better Addressing to the Experimental Needs.

机译:Madere Radio-Activity测量平台:发展到实验需求的更好地解决。

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The main goal of the Reactor Dosimetry is to provide information (reaction rates, fluence, fluence rate...) for the interpretation of experiments irradiated in critical mock-up, test reactors or power nuclear reactors. Various techniques are used, including analysis of irradiated activation or fission dosimeters whose radioactivity is measured afterwards. The MADERE platform (Measurement Applied to DosimEtry for REactors) is a CEA facility which is dedicated to the activation dosimeters manufacturing and their activity measurement after irradiation in a nuclear reactor. The laboratory is accredited by the French Accreditation Committee for specific activity measurements of solid samples using gamma and X-rays spectrometry. The choice of dosimeters takes into account limitations coming from the characteristics of the measurement devices. To meet experimenter's new demands, the MADERE platform set out to improve its offer by lowering the energy of measured radiations down to 10 keV, and the activity level down to the tenth of Becquerel (Bq). Doing so, the range of usable dosimeters and by the way, the energy range of the neutron spectrum is expanded. Dosimeter, wires or foils, few millimeters large, are manufactured using ultra-pure material (Gold, Iron, Nickel, ...). Some of them are encapsulated in quartz containers for integration into experimental devices. In order to determine the activity of irradiated metal solid samples, the MADERE platform makes use of several measurement equipments: 1. Three Gamma spectrometry devices equipped with semiconductor diode detectors HPGe set to work on an energy field ranging from 50 keV to 2 MeV. The range of activity covered by these devices spreads from a few tenths of Bq to a few tens of MBq. The ability to measure samples with activities of the order of one tenth of Bq may be used to implement a nondestructive determination of the isotopic composition of low-active objects. 2. One X-ray spectrometry device equipped with a LEGE (Low Energy GErmanium) GeHP semiconductor detector. The settings of this equipment have been made to work in an energy range from 10 keV to 300 keV. This range allows covering almost all the X energy domain and also easily measuring low energy gamma emitters. For a long time, this device has been exclusively used for relative activity measurements of irradiated niobium using a ~(93)Nb~m reference sample (17 keV Xk emitter). This direct comparison measurement method allows getting free from the determination of different measurement parameters, since they are considered proportional between the reference and the measured samples, under the hypothesis that geometry, activity level and measurement conditions are identical. A need has emerged for measuring the ~(103)(Rh~m) activity. It would have required the use of a reference ~(103)(Rh~m) source which is in fact excluded due to the short half-life (56 minutes) of this radionuclide. It was therefore decided to establish the total absorption yield curve in order to perform absolute activity measurement. 3. One precise micro-balance allowing the measurement of sample mass with an accuracy of few micrograms. 4. One fissile measurement device equipped with 4 Nal detectors associated to an automated samples holder. The quality of gamma spectrometry measurements mainly depends on the knowledge of the detection efficiency yield associated to the Source-Detector system geometry. Thus, the MADERE platform uses twenty different calibrated measurement geometries. In order to optimize the time spent on the experimental determination Of each associated detection yield, a modeling work is underway, using the ETNA software, developed by the Henri Becquerel French National Primary Laboratory, to derived transfer efficiency and correction coincidence parameters. The precise determination of the sample activity also requires the use of correction factors related to the effects of self absorption, sum peak and geometry. Thus, the MADE
机译:该反应堆剂量学的主要目的是为在关键的实物模型,试验堆或功率的核反应堆照射实验解释说明信息(反应速度,能量密度,能量密度率......)。使用各种技术,包括照射激活或裂变剂量计是继测量其放射性分析。所述MADERE平台(测量施加到剂量测定反应堆)是CEA设施,其在核反应堆专用于激活剂量计的制造和它们的活性测量照射后。该实验室由法国认可委员会采用γ射线和X射线光谱法固体样品的比活度测量认可。剂量计的选择考虑到限制从测量设备的特性来。为了满足实验者的新要求,MADERE平台着手改善降低测量辐射的能量下降到10千电子伏的报价,和活动水平下降到贝克勒尔(Bq)为第十。这样做时,可使用的剂量计,以及通过方式的范围内,中子谱的能量范围被扩展。剂量计,电线或箔,几毫米大,使用超纯材料制造(金,铁,镍,...)。他们中有些人被封装在集成到实验装置的石英容器。为了确定照射金属固体样品的活性,MADERE平台利用多个测量设备:1.配备有半导体二极管检测器的HPGe集合到工作于能量场范围从50keV至2MeV的三个伽马分析装置。活性范围覆盖从贝的十分之几到几十活度的这些设备差。以测量与贝的十分之一的数量级的活动样本的能力可被用来实现低活动对象的同位素组成的非破坏性测定。 2.配备有LEGE(低能量的锗)GeHP半导体检测器的一个X射线光谱设备。本设备的设置已经作出的工作在能量范围从10千电子伏至300千电子伏。这个范围允许覆盖几乎所有的X能量域,并且还容易地测量低能量γ发射体。在很长一段时间,该装置已被专门用于使用〜照射铌的相对活性的测量(93)的Nb〜米参照样品(17千电子伏值Xk发射极)。这种直接比较测量方法允许获得从不同的测量参数的确定自由,因为它们被认为是参考和测量的样品之间的比例,这一假设的几何形状,活动水平和测量条件相同下。甲需要已经出现用于测量〜(103)(铑〜m)的活性。这本来需要使用参考〜(103)(铑〜m)的源,其实际上是在排除了由于这种放射性核素的半衰期短(56分钟)。因此,决定建立,以执行绝对活性测量的总吸收产率曲线。 3.一个精确微平衡,允许样品质量的测量用几微克的精度。配备有相关联的自动化的样品保持器4个的NaI检测器4的一个裂变测量装置。 γ射线光谱测量的质量主要依赖于相关联的源 - 检测器系统的几何形状的检测效率产率的知识。因此,MADERE平台使用二十个不同的校准测量的几何形状。为了优化花在实验测定每个相关检测产量时,建模工作正在进行,使用ETNA软件,由亨利·贝克勒尔法国国民小学实验室开发,以衍生的转移效率和校正参数一致。样品活性的精确测定也需要使用相关的自吸收,总和峰和几何形状的影响校正因子。因此,MADE

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