核能

[中文适用范围]： 本文件描述了剂量计和剂量率计响应的校准和确定程序，这些响应是按照国际辐射单位和测量委员会 (ICRU) 定义的辐射防护操作量进行的。但是，正如 ICRU56[2] 中所述，用于区域监测的环境剂量当量 H*(10) 和用于个人监测的个人剂量当量 Hp(10) 不是任何 β 辐射的适当量，即使是穿透 10 毫米组织的辐射 (Emax > 2 MeV)。本文件是为那些使用 β 参考辐射校准防护级剂量计和剂量率计并确定其响应作为 β 粒子能量和入射角函数的人提供的指南。此类测量可以代表类型测试的一部分，在此过程中将检查其他影响量对响应的影响。本文件不涵盖固定安装的区域剂量计的现场校准。 “剂量计”一词用作通用术语，表示用于个人或区域监测的任何剂量或剂量率计。除了校准程序的描述外，本文件还包括有关适当模型的建议以及确定适当转换系数的方法。提供了有关测量不确定度声明和校准记录和证书准备的指导。 [外文原描述]： This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, the ambient dose equivalent, H *(10), used for area monitoring, and the personal dose equivalent, H p (10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue ( E max > 2 MeV). This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters with beta-reference radiation and determine their response as a function of beta-particle energy and angle of incidence. Such measurements can represent part of a type test during the course of which the effect of other influence quantities on the response is examined. This document does not cover the in-situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description of calibration procedures, this document includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.