A58 电离辐射计量 标准查询与下载

ISO 4037-2:1997 校准剂量仪和剂量率仪及确定其光子能量响应的Χ和γ参考辐射 第2部分:能量范围在8KeV-1、3MeV和4MeV-9MeV辐射防护剂量测定

This part of ISO 4037 specifies the procedures for the dosimetry of X and gamma reference radiation for the calibration of radiation protection instruments over the energy range from approximately 8 keV to 1,3 MeV and from 4 MeV to 9 MeV. The methods of production and nominal kerma rates obtained from these reference radiations are given in ISO 4037-1.

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 2: Dosimetry for radiation protection over the energy ranges 8 keV to 1,3 MeV and 4 MeV to 9 MeV

KS A 4422-1997 放射性灰尘采集器

이 규격은 방사선 방호를 목적으로 시설의 작업 환경 및 주변 환경과 시설의 배기계 등에서

Radioactive dust samplers

KS A 4421-1997 放射性灰尘探测器

이 규격은 방사선 방어를 목적으로 시설의 작업 환경, 주변 환경 및 시설의 배기 시설 등에

Radioactive dust monitors

KS A 4729-1997 反X线散射网格

이 규격은 X선 조사에 의해 피검사자의 체내에서 산란 X선이 X선 수상면에 입사되는 양을

Anti - scatter grids

KS A 4702-1997 电容式胸部X射线荧光屏图像摄影装置

이 규격은 공칭 전압 200V에 단상 교류 전원에서 사용하는 흉부 간접 촬영용 X선 장치

Capacitor discharge X- ray apparatus for chest indirect radiography

KS A 4727-1997 工业用X射线设备的有效焦点尺寸测定法

이 규격은 초점의 크기가 300㎛ 이상의 X선 투과 시험에 이용되는 공업용 X선 장치의 유

Measurement of the effective focal spot size for industrial X-ray apparatus

KS A 4802-1997 胸部X射线荧光屏图像摄影用防护箱子

이 규격은 X선 흉부 간접 촬영을 할 때 환자로부터 방사하는 산란선 및 X선원 장치에서의

Protective boxes for mass chest indirect radiography

KS A 4728-1997 X射线摄影胶片用名称打印机

이 규격은 X선 검사 의뢰표, 조사 기록, 인증카드 등에 기록되어 있는 문자, 기호 등을

Name printers for radiographic films

KS A 4726-1997 放射性碘采样机

이 규격은 원자력 시설의 작업 환경 및 주변 환경 또는 시설 내의 배기 계통의 공기 중에

Radioactive iodine samplers

KS A 4732-1997 医用诊断X线可变挡板

이 규격은 진단에 사용하는 의료용 X선관 장치 및 일체형 X선 발행 장치에 부착하고 X선

Variable X- ray beam limiting devices for diagnostic use

ASTM E666-97 计算γ或X射线吸收剂量的标准实施规程

1.1 This practice presents a technique for calculating the absorbed dose in a material from knowledge of the radiation field, the composition of the material, (1) and a related measurement. The procedure is applicable for X and gamma radiation provided the energy of the photons fall within the range from 0.01 to 20 MeV. 1.2 A method is given for calculating the absorbed dose in a material from the knowledge of the absorbed dose in another material exposed to the same radiation field. The procedure is restricted to homogeneous materials composed of the elements for which absorption coefficients have been tabulated (2). It also requires some knowledge of the energy spectrum of the radiation field produced by the source under consideration. Generally, the accuracy of this method is limited by the accuracy to which the energy spectrum of the radiation field is known. 1.3 The results of this practice are only valid if charged particle equilibrium exists in the material and at the depth of interest. Thus, this practice is not applicable for determining absorbed dose in the immediate vicinity of boundaries between materials of widely differing atomic numbers. For more information on this topic, see Practice E1249. 1.4 This practice does not consider dose "buildup" due to broad-beam geometry. Such "buildup" depends on the energy spectrum of the radiation field and the effective atomic number of the material. Correction can be made if buildup factors are included in the attenuation calculation. These factors have not been tabulated for a wide range of energies, geometries, and materials (3,4,5). However, this method has utility in providing a quick and relatively simple way of achieving useful approximate results. 1.5 Energy transport computer codes exist that are formulated to calculate absorbed dose in materials more precisely than this method. To use these codes, more effort, time, and expense are required. If the situation warrants, such calculations should be used rather than the method described here. 1.6 This standard does not purport to address all of the safety problems, 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 Practice for Calculating Absorbed Dose From Gamma or X Radiation

JJG 395-1997 定碳定硫分析仪检定规程

Verification Regulation of Carbon-Sulfur Analyzer

JJG 925-1997 净全辐射表检定规程

Verification Regulation of Net Pyrradiometer

KS A 4609-1996 医用X线影像增强设备

이 규격은 KS A 4021에 규정한 의료용 X선 장치인 영상 장치로 사용하는 X선 영상

Medical X-ray image intensifiers

KS A 4722-1996 医用X射线设备用高压电插头及插座

이 규격은 KS A 4201, KS A 4022 및 KS A 4701에 규정된 X선 고전압

High voltage cable plug and socket for medical X-ray equipment

KS A 4723-1996 医用X射线设备用高压电线(有插头)

이 규격은 KS A 4022 및 KS A 4701에 규정된 고전압 발생 장치와 X선관 장치

High voltage cables with plugs for medical X-ray equipment

ISO 4037-1:1996 校准剂量仪和剂量率仪及确定其光子能量响应的Χ和γ参考辐射 第1部分:辐射特性产生方法

Specifies the characteristics and production methods of X and gamma reference radiation for calibrating dosemeters and rate dosemeters at air kerma rates from 10 Gy/h to 10 Gy/h and for determining their response as a function of photon energy.

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy - Part 1: Radiation characteristics production methods

ISO 6980:1996 校准剂量仪和剂量率仪及确定其β辐射能量响应的β参考辐射

This International Standard specifies the requirements for reference beta radiations produced by radionuclide sources to be used for the calibration of protection level dosimeters and dose-rate meters, and for the determination of their response as a function of beta particle energy. It gives the characteristics of radionuclides which have been used to produce reference beta radiations, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose-equivalent rate at a depth of 7 mg·cm in the ICRU sphere. The energy range involved lies between 66 keV and 3,6 MeV and the absorbed dose rates are in the range from about 10μSv·h to at least 10 Sv·h. In addition, for some sources variations of the absorbed dose rate as a function of the angle of incidence are given. This International Standard proposes two series of reference beta radiations from which the radiation necessary for determining the characteristics (calibration and energy response) of an instrument should be selected. Series 1 reference radiations are produced by radionuclide sources used with beam-flattening filters designed to give uniform dose rates over a large area at a specified distance. The proposed sources of Sr + Y, TI and Pm produce maximum dose rates of approximately 5 mSv·h. Series 2 reference radiations are produced without the use of beam-flattening filters, which allows planar sources of large area and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this Series has the advantage of extending the energy and dose rate ranges beyond those of Series 1. The radionuclides used are those of Series 1 with the addition of the radionuclides C and Ru + Rh; these sources produce dose rates of up to 10 Sv·h. note: 1) These also include personal dosimeters. 2) This lower limit of the energies to be considered represents the energy of beta particles able to reach the sensitive layer of the skin which is situated nominally 7 mg·cm below the skin surface according to ICRP 60.

Reference beta radiations for calibrating dosimeters and dose-rate meters and for determining their response as a function of beta-radiation energy

ASTM E704-96(2002) 用铀238的放射激活性测定反应速率的测试方法

1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction 238U(n,f)F.P.1.2 The reaction is useful for measuring neutrons with energies from approximately to 7 MeV and for irradiation times up to 30 to 40 years.1.3 Equivalent fission neutron fluence rates as defined in Practice E 261 can be determined.1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E 261.1.5 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 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238

ASTM E704-96 用铀238的放射激活性测定反应速率的测试方法

1.1 This test method covers procedures for measuring reaction rates by assaying a fission product (F.P.) from the fission reaction 238 U(n,f)F.P. 1.2 The reaction is useful for measuring neutrons with energies from approximately 1.5 to 7 MeV and for irradiation times up to 30 to 40 years. 1.3 Equivalent fission neutron fluence rates as defined in Practice E261 can be determined. 1.4 Detailed procedures for other fast-neutron detectors are referenced in Practice E261. 1.5 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 Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238