首页> 外文会议>The Tenth International Symposium on Reactor Dosimetry, Sep 12-17, 1999, Osaka, Japan >Neutron and Gamma Ray Dosimetry in Spent-Fuel Radiation Environments Using Silicon Carbide Semiconductor Radiation Detectors
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Neutron and Gamma Ray Dosimetry in Spent-Fuel Radiation Environments Using Silicon Carbide Semiconductor Radiation Detectors

机译:使用碳化硅半导体辐射探测器在乏燃料辐射环境中进行中子和伽马射线剂量测定

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摘要

Silicon carbide semiconductor radiation detectors are resistant to radiation-induced damage and can be operated at elevated and changing temperatures.. Silicon carbide radiation detectors have been shown to have linear responses to both neutrons and gamma rays. Furthermore, these responses are separable on the basis of pulse height, making simultaneous monitoring of both neutrons and gamma rays possible. The neutron and gamma ray sensitivities of silicon carbide radiation detectors are well-matched to the radiation environments characteristic of spent nuclear fuel. Measurements have been carried out in mixed gammaeutron fields in a hot cell and at a reactor facility under conditions chosen to approximate the radiation fields typically encountered in the vicinity of spent nuclear fuel assemblies. The results of these measurements and the application of silicon carbide radiation detectors to spent fuel dosimetry are discussed.
机译:碳化硅半导体辐射探测器能够抵抗辐射引起的损害,并且可以在升高的温度和变化的温度下运行。碳化硅辐射探测器已显示出对中子和伽马射线均具有线性响应。此外,这些响应在脉冲高度的基础上是可分离的,从而可以同时监视中子和伽马射线。碳化硅辐射探测器的中子和伽马射线灵敏度与乏核燃料的特征辐射环境非常匹配。已经在热室中和反应堆设施中的混合伽马/中子场中,在选定的条件下进行了测量,这些条件被选择为近似于乏核燃料组件附近通常遇到的辐射场。讨论了这些测量的结果以及碳化硅辐射探测器在乏燃料剂量测定中的应用。

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