A58 电离辐射计量 标准查询与下载

KS A 4724-2006 室内环境监测用胶片佩章

이 규격은 실내 환경에서 실효 에너지가 20 keV 3 ∼ MeV인 X선, 광자 에너지가

Film badge for in－door environmental monitoring

JJF 1035-2006 电离辐射计量术语及定义

本规范供制定、修订电离辐射计量技术法规使用，在计量工作的其他方面及相关科技领域亦可参考使用。

Metrological Terms and Their Definitions for Ionizing Radiation

KS A 4808-2006 放射性物质处理作业用手套式操作箱

이 규격은 방사성 물질을 취급하는 작업장 등에서 사용하는 글러브 박스에 대하여 규정한다.

Glove box for handling of readioN substance

JJG 852-2006 中子周围剂量当量(率)仪检定规程

本规程适用于中子周围剂量当量（率）仪的首次检定、后续检定和使用中检验，其他中子剂量仪表的检定、校准工作也可参照使用。

Verification Regulation of Neutron Ambient Dose Equivalent (Rate) Meters

JJG 417-2006 γ谱仪检定规程

本规程适用于γ谱仪的首次检定、后续检定和使用中检验。γ谱仪包括碘化钠γ谱仪和半导体γ谱仪。

Verification Regulation of γ Ray Spectrometers

KS A 4446-2006 X线机管电压测试机

이 규격은 KS A 4021에 적합한 의료용 X선 장치의 관전압을 측정하는 X선 관전압에

Measuring devices for X－ray tube voltage

KS A 4522-2006 高速中子用胶片佩章.辐射剂量当量计算法

이 규격은 개인 모니터링을 위하여 에너지가 0.5∼15 MeV 범위인 고속 중성자용 필름

Methods of evaluating dose equivalent by fast neutron film badges

KS A 4444-2006 残留X线屏蔽设备

이 규격은 진단에 사용하는 콘덴서식 X선 고전압 장치, 제어형 X선관 장치 및 KS A 4

Shielding devices for stand－by radiation

KS A 4610-2006 X线及γ线用辐射剂量当量测量仪

이 규격은 X선 및 γ 선의 1 cm 선량 당량률을 측정하는 방사선 서베이미터(이하, 서베

Portable photon ambient dose equivalent ratemeters for radiation protection

KS A 4321-2006 放射线探测用碘化钠闪烁探测器

이 규격은 γ 선 및 X선의 측정에 사용하는 지름 및 높이가 127 mm 이하 크기의 활성

Thallium－activated sodium iodide scintillator for radiation detection

KS A 4614-2006 放射线应用测计器用电离辐射容器

이 규격은 3.7 MBq를 넘는 밀봉 방사선원을 수납하는 용기로, 방사선 응용 계측기에 사

Surface container of measuring instrument utilizing ionizing radiation

KS A 4817-2006 放射线屏蔽用铅砖

이 규격은 원자력 관련 사업장에서 방사성 동위 원소, 방사선 발생 장치 등을 취급할 때 X

Radiation shielding lead bricks

KS A 4443-2006 环境γ线连续监视器

이 규격은 원자력 시설 및 방사선 시설의 주변에 설치되어, 환경 γ 선의 선량률을 연속적으

Continuous type environmental γ -ray monitors

KS A 4905-2006 医用放射线胶片录音带

이 규격은 진료를 목적으로 방사선 촬영을 할 때, KS A 4912에 규정하는 의료용 X선

Radiographic cassettes for medical use

BS ISO 6980-3:2006 核能.参考β粒子辐射.β辐射能量函数和入射角度的区域校准及个人剂量计和它们响应的测定

This part of ISO 6980 describes procedures for calibrating and determining the response of dosemeters and doserate meters in terms of the International Commission on Radiation Units and Measurements (ICRU) operational quantities for radiation protection purposes. However, as noted in ICRU Report 56, the ambient dose equivalent, H(10), used for area monitoring of strongly penetrating radiation, is not an appropriate quantity for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV). For beta particles, the calibration and the determination of the response of dosemeters and doserate meters is essentially a three-step process. First, the basic field quantity, absorbed dose to tissue at a depth of 0,07 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 part of ISO 6980 describes the methods and the conversion coefficients to be used for the determination of the response of dosemeters and doserate meters in terms of the ICRU operational quantities directional dose equivalent, H(0.07Ω) and personal dose equivalent, Hp(0,07). This part of ISO 6980 is a guide for those who calibrate protection-level dosemeters and doserate 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 part of ISO 6980 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 doserate meter for individual or area monitoring. In addition to the description of calibration procedures, this part of ISO 6980 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.

Nuclear energy - Reference beta-particle radiation - Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

ISO 6980-3:2006 核能.基准β粒子辐射.第3部分:校准区域和个人计量及测定作为β辐射能量和入射角函数的β能量响应

This part of ISO 6980 describes procedures for calibrating and determining the response of dosemeters and doserate meters in terms of the International Commission on Radiation Units and Measurements (ICRU) operational quantities for radiation protection purposes. However, as noted in ICRU Report 56, the ambient dose equivalent, H(10), used for area monitoring of strongly penetrating radiation, is not an appropriate quantity for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV). For beta particles, the calibration and the determination of the response of dosemeters and doserate meters is essentially a three-step process. First, the basic field quantity, absorbed dose to tissue at a depth of 0,07 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 part of ISO 6980 describes the methods and the conversion coefficients to be used for the determination of the response of dosemeters and doserate meters in terms of the ICRU operational quantities directional dose equivalent, H(0.07Ω) and personal dose equivalent, Hp(0,07). This part of ISO 6980 is a guide for those who calibrate protection-level dosemeters and doserate 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 part of ISO 6980 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 doserate meter for individual or area monitoring. In addition to the description of calibration procedures, this part of ISO 6980 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.

Nuclear energy - Reference beta-particle radiation - Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

ISO 6980-1:2006 核能.β粒子辐射基准.第1部分:中子生产方法

GB／T 12164的本部分规定了利用放射性核素源产生的β参考辐射场的要求。给出了这些放射性 核素的特性和适当的源结构的示例，并且描述了β粒子最大剩余能量以及在ICRU球中深度0．07 mm 处剂量当量率的测量方法。能量范围为66 keV～3．6 MeV，剂量当量率范围从大约10 μSv·h到至 少10 Sv·h。此外，还给出了一些源剂量当量率随入射角度的变化。本部分适用于确定H(O．07) 和H’(O．07)的个人和场所剂量(率)仪的校准，以及它们能量响应和角响应的确定。 GB／T 12164的本部分推荐了两个系列的β参考辐射场，可从中选取确定仪表特性(校准以及确定 能量响应和角响应)所需的辐射。 系列1参考辐射场由配有束展平过滤器的放射性核素源产生，使得在指定距离处大面积上给出均 匀的剂量当量率。该系列的源包括Sr+Y、Kr、Tl和Pm，产生的最大剂量当量率大约 200 mSv·h。 系列2参考辐射场不带展平过滤器，可使用大面积平面源，并且源到校准平面的距离可在一定范围 内调节。在靠近这些源时，只在相对小的面积上剂量率是均匀的，但该系列具有对系列1能量和剂量率 范围扩展的优点。使用的放射性核素除系列1外，增加了C和Ru+Rh，这些源产生的剂量率可达 10 Sv·h。

Nuclear energy - Reference beta-particle radiation - Part 1: Methods of production

JIS Z 4521:2006 中子剂量当量(比率)计的校准方法

この規格は，放射線防護の目的で使用する中性子線量当量(率)計の校正方法のうち，熱 中性子から20 MeVまでのエネルギー範囲における基準中性子を用いるものの校正方法について規定する

Method of calibration for neutron dose equivalent (rate) meters

BS EN 14255-2:2005 暴露在非相干光辐射中的人体测量和评定.第2部分:工作场所中人工源放射的可见和红外线辐射

This European Standard specifies procedures for the measurement and assessment of personal exposures to visible (VIS) and infrared (IR) radiation emitted by artificial sources, where adverse effects cannot be readily excluded. NOTE 1 Adverse effects will normally not occur in exposures caused by normal lighting or room heating. This European Standard applies to VIS- and IR- exposures in indoor and outdoor workplaces. It does not apply to VIS- and IR-exposures in leisure time. This European Standard does not apply to VIS- and IR- exposures caused by the sun. NOTE 2 Part 3 of this standard will deal with UV-exposures caused by the sun. This European Standard does not specify VIS- and IR-exposure limit values. It supports the application of limit values set by national regulations or international recommendations. This European Standard applies to VIS- and IR- exposures by artificial incoherent sources, which emit spectral lines as well as continuous spectra. This European Standard does not apply to coherent radiation sources. NOTE 3 Coherent optical radiation sources are covered by standards for lasers, like EN 60825-1 etc. This European Standard applies to visible (VIS) and infrared (IR) radiation exposures in the wavelength band 380 nm to 3 μm. It also applies to radiation exposures that may present a blue-light hazard in the wavelength band 300 nm to 700 nm. This European Standard does not apply to other effects of which the action spectra lie solely within the UV-region 180 nm to 400 nm. NOTE 4 Part 1 of EN 14255 addresses these effects. This European Standard does not apply to radiation emissions of products. NOTE 5 For radiation emissions of products other standards apply, such as EN 12198 for radiation emissions of machinery, EN 60335-2-27 for household appliances for skin exposures to ultraviolet and infrared radiation and CIE S009 for the safety of lamps and lamp systems. This European Standard does not apply to heat stress, i.e. long term heating of the humans body with strain of the cardiac/circular system caused by climatic environmental conditions including VIS/IR radiation.

Measurement and assessment of personal exposures to incoherent optical radiation - Part 2: Visible and infrared radiation emitted by artificial sources in the workplace

ASTM D7316-06 影响应急反应决定的现有现场仪器说明用标准指南

This guide is intended for use by field personnel for the rapid evaluation of the presence of and type of radioactive materials, based on information obtained from available field instrumentation. Guidance is offered for actions which may be taken to better understand the instrument indications for various scenarios, and guidance is offered for personnel protection and consultation with additional appropriate authorities. This guide does not include policy or procedures for radiation health protection. Such policy and procedures are determined locally by the organization(s) involved (site, city, county, state, federal). The policies and procedures may vary between organizations and may be dependent on the type of radiological incident. Users of this guide should be familiar with the policies of their local organizations.1.1 The objective of this guide is to provide useful information for the interpretation of radiological instrument responses in the event of a radiological incident or emergency.1.2 For the purposes of this guide, a radiological incident or emergency is defined as those events that follow the indication of the presence of radioactive material outside of a Department of Energy (DOE) or Nuclear Regulatory Commission (NRC) defined radiological area. The event may be triggered by a law enforcement officer wearing a radiation pager during the course of his routine duties, a first responder at the scene of an accident wearing a radiation pager, a HAZMAT team responding to the scene of an accident known to involve radioactive material surveying the area, etc.This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Interpretation of Existing Field Instrumentation to Influence Emergency Response Decisions