Fast neutron irradiation effects—I. Dosimetry

Radiation Physics and Chemistry (1977) Pub Date : 1985-01-01 DOI:10.1016/0146-5724(85)90188-8

Y Katsumura , Y Tabata, T Seguchi, N Hayakawa, K Yoshida, N Tamura

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引用次数: 15

Abstract

A dosimetry of mixed field, neutron and γ-ray, has been carried out by the activation method in a fast neutron source reactor “YAYOI,” which has been used for the study of fast neutron irradiation effects on organic materials and microorganisms. Neutron flux and energy distribution were obtained by an unfolding calculation based on the activation analysis. Absorbed dose was determined as a function of the distance from the center of the reactor core in a hole called “Glory Hole” used for irradiation of various materials. Contribution of absorbed dose from γ-rays coexisting with neutron was evaluated by measuring peroxide radicals formed in irradiated polytetrafluoroethylene, PTFE, which is insensitive to the neutron component. After evaluating the radiation field, relative sensitivities of popular dosimeters such as red acrylate, radiachromic, and alanine dosimeter for last neutron irradiation were determined by comparison with ⁶⁰Co γ-ray irradiation. Characteristics of the mixed field dosimetry and LET effect of recoil protons in samples at different neutron fields are discussed.

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快中子辐照效应——ⅰ。剂量测定法

在快中子源反应堆“YAYOI”中，用活化法进行了中子和γ射线混合场剂量学，该反应堆已用于研究快中子辐照对有机材料和微生物的影响。在活化分析的基础上，通过展开计算得到了中子通量和能量分布。吸收剂量是根据一个被称为“荣耀洞”的洞中距离反应堆堆芯中心的距离来确定的，这个洞用于各种材料的辐照。通过测量对中子成分不敏感的聚四氟乙烯(PTFE)在辐照后形成的过氧化物自由基，评价了与中子共存的γ射线对吸收剂量的贡献。在评价辐射场的基础上，通过与60Co γ射线辐照比较，确定了红丙烯酸酯、辐射消色差、丙氨酸等常用剂量计对末次中子辐照的相对灵敏度。讨论了不同中子场下样品中反冲质子的混合场剂量学特征和LET效应。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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