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Reduction of the External Dose Rate of a Research Nuclear Reactor Shielding Utilizing Concrete with Higher Incorporated Water Quantity

机译:减少掺入水量较高的使用混凝土的研究用核反应堆的外剂量率降低

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The ordinary concrete used in constructions hold about 4 wt% to 6 wt% of water content in itsmixtures under two distinct fractions: free water fraction and chemically constituted water fraction. Studies havebeen showing that is possible and convenient to increase 3 to 4 wt% the water content in the special concretemixtures used in nuclear reactor shielding, increasing the free water fraction and yet considering an adequateconcrete composition of the components in order not to compromise the structural resistance with the increasedwater to cement ratio. This is technically viable, because these structures have dimensions much superior thanthose imposed by structural calculations since they are determined as a function of the shielding design itself.The use of a concrete with larger quantity of incorporated water assures a more efficient neutron capture processin the foremost concrete shielding layers leaving a great portion of material thickness to attenuate the highenergygamma radiation resulting from these neutron captures. This in turn reduces the dose rate in the externalshielding wall satisfying the ALARA principle, and assures a less radioactive environment in the reactorsurroundings, which is important for the procedures of radiological protection of the installation. This workevaluated the reduction of the dose rate in the outer wall of the shielding of a reactor type pool of 10 MWth dueto variations of the water fraction content in concrete, in a range from 4 to 7 wt%. This variation range waschosen conservatively and took into account the free water fraction incorporated into an ordinary concrete andexperimentally estimated through neutron radiography techniques carried using the irradiation channel of theArgonauta reactor installed at the Instituto de Engenharia Nuclear. The discrete ordinate code ANISN, theEURLIB4 library of neutrons and gammas, and heavy concrete of different densities were used in thecalculations.
机译:建筑中使用的普通混凝土在其混凝土中可容纳约4 wt%至6 wt%的水含量 两种不同馏分的混合物:游离水馏分和化学组成的水馏分。研究有 结果表明,可以将特殊混凝土中的水含量提高3至4 wt%,并且很方便 核反应堆防护中使用的混合气,增加了自由水的比例,但仍在考虑适当的混合 组件的混凝土组成,以便不因增加结构阻力而受到损害 水灰比。这在技术上是可行的,因为这些结构的尺寸比 由于它们是根据屏蔽设计本身来确定的,因此它们是由结构计算所强加的。 掺入大量水的混凝土的使用可确保更有效的中子捕获过程 在最前面的混凝土屏蔽层中留有很大一部分材料厚度,以减弱高能 这些中子俘获所产生的伽马辐射。反过来,这降低了外用药的剂量率 满足ALARA原则的屏蔽墙,并确保反应堆中的放射性环境更少 周围环境,对于设备的放射防护程序很重要。这项工作 评估了由于反应堆式池10兆瓦时的屏蔽层外壁剂量率的降低 混凝土中水含量的变化范围为4至7重量%。该变化范围为 谨慎选择,并考虑到掺入普通混凝土中的自由水部分,以及 通过中子射线照相技术通过使用 安装在恩根哈里亚核研究所的Argonauta反应堆。离散纵坐标代码ANISN, EURLIB4中子和γ的库,以及不同密度的重混凝土被用于 计算。

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