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首页> 外文期刊>EPJ Web of Conferences >EVALUATION OF THE DOSE LEVELS IN THE IRRADIATION CHANNELS OF PU-BE NEUTRON SOURCES STORAGE DEVICE BY USING NEUTRON ACTIVATION ANALYSIS AND MCNP6 MODELLING
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EVALUATION OF THE DOSE LEVELS IN THE IRRADIATION CHANNELS OF PU-BE NEUTRON SOURCES STORAGE DEVICE BY USING NEUTRON ACTIVATION ANALYSIS AND MCNP6 MODELLING

机译:利用中子激活分析和MCNP6造型评估PU - 中子源存储装置的照射通道中的剂量水平

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PuBeneutrons sources of Educational Neutron Laboratory in the Center for Physical Sciences and Technology are used in several activities including neutron activation for educational purposes and laboratory irradiation experiments. In this work we address the dose rate estimation in the irradiation channels of reconstructed PuBe neutron sources storage device in the particular positions dedicated for neutron irradiation experiments using neutron activation analysis (NAA) and MCNP6 modelling.The results on neutron activation of V_(2)O_(5), MnO_(2), Al and Na_(2)CO_(3)were analyzed and compared with MCNP6 model prediction results. The conclusions on the actual neutron flux energy distribution and model corrections are drawn. The absolute neutron intensity at dedicated irradiation points as well as neutron and gamma dose rates are obtained.
机译:在若干活动中使用了物理科学和技术中心的教育中子实验室的公文来源,包括用于教育目的和实验室辐照实验的中子激活。 在这项工作中,我们在使用中子激活分析(NAA)和MCNP6型型中子照射实验的特定位置中,在专用于中子辐射实验的特定位置处地解决了辐射通道的剂量率估计。结果对V_(2)的中子激活结果 分析O_(5),MNO_(2),AL和NA_(2)CO_(3)与MCNP6模型预测结果进行了比较。 拉伸关于实际中子磁通能量分布和模型校正的结论。 获得专用照射点以及中子和γ剂量率的绝对中子强度。

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