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Status of Prompt Gamma Neutron Activation Analysis at TRR-1/MI

机译:瞬发伽马中子活化分析在TRR-1 / MI中的状态

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The first prompt gamma activation analysis was designed, constructerd and installed at a 6 inch diameter neutron beam port of hte Thai Research Reactor-1/Modified 1 since 1989. Beam characteristics were made by Gd foil irradiation, X-ray film exposing and densitometry scanning consequently. The thermal neutron flux at sample position was measured by au foil activation, and was about 1*10 sup 7 n.cm sup 2.sec sup -1 at 700 KW operating power. The experiments have bee nconducted successfuly. In 1998, the PGAA facility has ben developed for hte reactor operating power at 1.2 MW. The new PGAA system, e.g., beam shutter, gamma ocllimator and biological shields have been designed to reduce the leakage of neutrons nad gamma radiation to the acceptance levels in accordance with the internatioinal commission on Radiatin Protection Publication 60. The construction and installation will be completed in April 1999.
机译:自1989年以来,首次设计,构造和安装了首次快速伽马活化分析,并将其安装在Thai Research Reactor-1 / Modified 1的6英寸直径中子束端口。通过Gd箔辐射,X射线胶片曝光和光密度测定法扫描来确定束流特征所以。通过金箔活化来测量样品位置处的热中子通量,并且在700KW的操作功率下约为1×10 sup 7 n.cm sup 2.sec sup -1。实验已成功进行。 1998年,开发了PGAA设施,以使反应堆的工作功率为1.2兆瓦。按照Radiatin保护出版物60的内部委员会规定,新的PGAA系统(例如,光束百叶窗,伽马射线定标器和生物防护罩)被设计为将中子和伽马射线的泄漏降低到可接受的水平。施工和安装将完成。在1999年4月。

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