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Calculation of Dose Equivalent Index, Effective Dose Equivalent and Ambient Dose Equivalent for the Giant Resonance Neutron Spectra Produced at an Electron Accelerator.

机译:计算电子加速器产生的巨大共振中子谱的剂量当量指数,有效剂量当量和环境剂量当量。

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The ANISN code has been used in this study to evaluate the attenuation of neutron beams of various spectra incident normally on slabs of different kinds of concrete. Spectra of the most common sources (Am-Be and Cf-252) and those of giant resonance neutrons, produced at electron accelerators, were studied. The concretes examined had densities between 2.1 and 4.64 g.cm/sup -3/. The calculation were made in terms of the deep dose equivalent index, the effective dose equivalent and the ambient dose equivalent. Values of attenuation length in the various materials were derived from the attenuation curves. The results found should allow for useful evaluations in every day practice for health physicists. (Atomindex citation 20:003965)

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