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※一部、英文及び仏文を自動翻訳した日本語訳を使用しています。
序章
ISO 6980 シリーズは、防護目的の線量計および線量率計の校正のためのベータ粒子基準放射線場の製造、校正、および使用をカバーしています。この文書では、線量計と線量率計の校正手順と、ベータ粒子のエネルギーとベータ粒子の入射角の関数としてのそれらの応答の決定について説明します。 ISO 6980-1 では、基準放射線の生成方法と特性評価について説明しています。 ISO 6980-2 には、ベータ粒子基準放射線場から組織の基準深さまでの吸収線量率を決定する手順が記載されています。
ベータ粒子の場合、線量計と線量率計の校正と応答の決定は、基本的に 3 段階のプロセスです。まず、ISO 6980 に記載されている方法を使用して、組織相当のスラブ形状における深さ 0.07 m, ならびに個人線量当量、 H p (0.07) およびH p (3)
Introduction
ISO 6980 series covers the production, calibration, and use of beta-particle reference radiation fields for the calibration of dosemeters and dose-rate meters for protection purposes. This document describes procedures for the calibration of dosemeters and dose-rate meters and the determination of their response as a function of beta-particle energy and angle of beta-particle incidence. ISO 6980-1 describes the methods of production and characterization of the reference radiation. ISO 6980-2 describes procedures for the determination of absorbed dose rate to a reference depth of tissue from beta particle reference radiation fields.
For beta particles, the calibration and the determination of the response of dosemeters and dose‑rate meters is essentially a three-step process. First, the basic field quantity, absorbed dose to tissue at a depth of 0,07 mm (and optionally also at a depth of 3 mm) in a tissue-equivalent slab geometry is measured at the point of test, using methods described in ISO 6980-2. Then, the appropriate operational quantity is derived by the application of a conversion coefficient that relates the quantity measured (reference absorbed dose) to the selected operational quantity for the selected irradiation geometry. Finally, the reference point of the device under test is placed at the point of test for the calibration and determination of the response of the dosemeter. Depending on the type of dosemeter under test, the irradiation is either carried out on a phantom or free-in-air for personal and area dosemeters, respectively. For individual and area monitoring, this document describes the methods and the conversion coefficients to be used for the determination of the response of dosemeters and dose-rate meters in terms of the ICRU operational quantities, i.e., directional dose equivalent, H′(0,07;Ω) and H′(3;Ω), as well as personal dose equivalent, Hp(0,07) and Hp(3).