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Development of a Neutron Radiography Facility at the Oregon State TRIGA~® Reactor

机译:在俄勒冈州TRIGA〜®反应堆中开发中子射线照相设施

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摘要

The Oregon State TRIGA Reactor (OSTR) is a 1.1-MW water-cooled, swimming pool type of research reactor that uses high enriched uranium/zirconium hydride matrix fuel elements in a circular grid array, surrounded by a graphite reflector. The OSTR first went critical in March 1967. Major irradiation facilities include a pneumatic transfer (rabbit) system, a rotating rack, a thermal column, sample holding dummy fuel elements, and two types of in-core vertical tubes. The OSTR also includes four beam ports for use in gamma and neutron radiography. In recent years a concentrated effort has been made to increase the utilization of the four beam ports. Beam ports 1, 2, and 4 are all radial in orientation to the core. Beam port 3 is tangentially oriented to the core, making it ideally suited for thermal neutron radiography.
机译:俄勒冈州TRIGA反应堆(OSTR)是1.1兆瓦的水冷游泳池型研究堆,其使用高浓度铀/氢化锆基体燃料元件呈圆形栅格阵列,被石墨反射器包围。 OSTR于1967年3月首次达到临界状态。主要的辐照设施包括气动传输(兔子)系统,旋转架,热柱,容纳虚拟燃料元件的样品以及两种类型的堆芯垂直管。 OSTR还包括四个用于伽马射线和中子射线照相的束口。近年来,人们集中精力增加了四个光束端口的利用率。梁端口1、2和4都相对于纤芯呈放射状。束口3与芯线相切,使其非常适合热中子射线照相。

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