F80 核仪器与核探测器综合 标准查询与下载

NF M60-812-2:2006 核能.测量环境放射性.第2部分:在环境碳材料中用液体闪烁法测量碳14活性

Nuclear energy - Measurement of environmental radioactivity - Part 2 : measurement of carbon 14 activity by liquid scintillation in carbon matrices in the environment.

JIS Z 4401:2006 辐射测量仪用试样盘

この規格は，放射性核種から放出される放射線を測定するための放射線測定用試料皿(以下，試料皿という。)について規定する。

Planchets used in radiation measurement instruments

GJB 519A-2006 核监测装备定型试验规程

本标准规定了核监测装备定型试验的基本要求、试验项目和试验程序。 本标准适用于便携式、固定式、车载、机载、舰载等各军兵种通用和专用的核监测装备的定型（鉴定）试验。

Approval test procedure for nuclear monitoring mateeiel

GJB 1469A-2006 核监测装备安全要求和试验方法

本标准规定了对核监测装备的电离辐射与放射性、电、机械、热、光等安全要求和试验方法。 本标准适用于便携式、固定式、车载、机载、舰载等各军兵种通用和专用的核监测装备（以下简称装备）。 本标准不适用于专门用于核监测装备计量校准用的辐射源装置。

Safety requirements and test methods for nuclear monitoring materiels

ASTM C1477-06 多收集器感应耦合等离子质谱法分析六氟化铀和硝酸铀酰溶液同位素丰度的标准试验方法

The test method is capable of measuring uranium isotopic abundances of 234U, 235U, 236U and 238U as required by Specifications C 787 and C 996.1.1 This test method covers the isotopic abundance analysis of 234U, 235U, 236U and 238U in samples of hydrolysed uranium hexafluoride (UF6) by inductively coupled plasma source, multi-collector, mass spectrometry (ICP-MC-MS). The method applies to material with 235U abundance in the range of 0.2 to 6 % mass. This test method is also described in ASTM STP 1344.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 Isotopic Abundance Analysis of Uranium Hexafluoride and Uranyl Nitrate Solutions by Multi-Collector, Inductively Coupled Plasma-Mass Spectrometry

ASTM E2059-06 快中子剂量测定用核研究乳剂的应用和分析标准规程

1.1 Nuclear Research Emulsions (NRE) have a long and illustrious history of applications in the physical sciences, earth sciences and biological sciences (,). In the physical sciences, NRE experiments have led to many fundamental discoveries in such diverse disciplines as nuclear physics, cosmic ray physics and high energy physics. In the applied physical sciences, NRE have been used in neutron physics experiments in both fission and fusion reactor environments (). Numerous NRE neutron experiments can be found in other applied disciplines, such as nuclear engineering, environmental monitoring and health physics. Given the breadth of NRE applications, there exist many textbooks and handbooks that provide considerable detail on the techniques used in the NRE method. As a consequence, this practice will be restricted to the application of the NRE method for neutron measurements in reactor physics and nuclear engineering with particular emphasis on neutron dosimetry in benchmark fields (see Matrix E 706).1.2 NRE are passive detectors and provide time integrated reaction rates. As a consequence, NRE provide fluence measurements without the need for time-dependent corrections, such as arise with radiometric (RM) dosimeters (see Test Method E 1005). NRE provide permanent records, so that optical microscopy observations can be carried out anytime after exposure. If necessary, NRE measurements can be repeated at any time to examine questionable data or to obtain refined results.1.3 Since NRE measurements are conducted with optical microscopes, high spatial resolution is afforded for fine structure experiments. The attribute of high spatial resolution can also be used to determine information on the angular anisotropy of the in-situ neutron field (,,). It is not possible for active detectors to provide such data because of in-situ perturbations and finite-size effects (see Section ).1.4 The existence of hydrogen as a major constituent of NRE affords neutron detection through neutron scattering on hydrogen, that is, the well known (n,p) reaction. NRE measurements in low power reactor environments have been predominantly based on this (n,p) reaction. NRE have also been used to measure the 6Li ( n,t) 4He and the 10B (n,) 7Li reactions by including 6Li and 10B in glass specks near the mid-plane of the NRE (,). Use of these two reactions does not provide the general advantages of the (n,p) reaction for neutron dosimetry in low power reactor environments (see Section ). As a consequence, this standard will be restricted to the use of the (n,p) reaction for neutron dosimetry in low power reactor environments.1.5 Limitations The NRE method possesses three major limitations for applicability in low power reactor environments.1.5.1 Gamma-Ray SensitivityGamma-rays create a significant limitation for NRE measurements. Above a gamma-ray exposure of approximately 3R, NRE can become fogged by gamma-ray induced electron events. At this level of gamma-ray exposure, neutron induced proton-recoil tracks can no longer be accurately measured. As a consequence, NRE experiments are limited to low power environments such as found in critical assemblies and benchmark fields. Moreover, applications are only possible in environments where the buildup of radioactivity, for example, fission products, is limited.1.5.2 Low Energy Limit In the measurement of track length for proton recoil events, track length decreases as proton-recoil energy decreases. Proton-recoil track length below approximately 3 in NRE can not be adequately measured with optical microscopy techniques. As proton-recoil track length decreases below approximately 3, it becomes very difficult to measure track length accurately. This 3 track length limit corresponds to a low energy limit of appli......

Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry

ANSI/ISA 67.04.01-2006 与核安全相关的仪器仪表设置

This standard defines the requirements for assessing, establishing, and maintaining nuclear safety-related and other important instrument setpoints associated with nuclear power plants or nuclear reactor facilities. The scope includes instrumentation-based setpoints that assure compliance to one or more design limits.

Setpoints for Nuclear Safety-Related Instrumentation

ASTM E2059-06(2010) 快中子剂量测定用核研究乳剂的应用和分析的标准操作规程

Integral Mode Dosimetry8212;As shown in 3.2, two different integral relationships can be established using proton-recoil emulsion data. These two integral reactions can be obtained with roughly an order of magnitude reduction in scanning effort. Consequently this integral mode is an important complementary alternative to the customary differential mode of NRE spectrometry. The integral mode can be applied over extended spatial regions, for example, perhaps up to as many as ten in-situ locations can be covered for the same scanning effort that is expended for a single differential measurement. Hence the integral mode is especially advantageous for dosimetry applications which require extensive spatial mapping, such as exist in Light Water Reactor-Pressure Vessel (LWR-PV) benchmark fields (see Test Method E1005). In low power benchmark fields, NRE can be used as integral dosimeters in a manner similar to RM, solid state track recorders (SSTR) and helium accumulation monitors (HAFM) neutron dosimeters (see Test Methods E854 and E910). In addition to spatial mapping advantages of these other dosimetry methods, NRE offer fine spatial resolution and can therefore be used in-situ for fine structure measurements. In integral mode scanning, both absolute reaction rates, that is I(ET) and J(Emin), are determined simultaneously. Separate software codes need to be used to permit operation of a computer based interactive system in the integral mode (see Section 9). It should be noted that the integrals I(ET) and J(Emin) possess different units, namely proton-recoil tracks/MeV per hydrogen atom and proton-recoil tracks per hydrogen atom, respectively.1.1 Nuclear Research Emulsions (NRE) have a long and illustrious history of applications in the physical sciences, earth sciences and biological sciences (1,2) . In the physical sciences, NRE experiments have led to many fundamental discoveries in such diverse disciplines as nuclear physics, cosmic ray physics and high energy physics. In the applied physical sciences, NRE have been used in neutron physics experiments in both fission and fusion reactor environments (3-6). Numerous NRE neutron experiments can be found in other applied disciplines, such as nuclear engineering, environmental monitoring and health physics. Given the breadth of NRE applications, there exist many textbooks and handbooks that provide considerable detail on the techniques used in the NRE method. As a consequence, this practice will be restricted to the application of the NRE method for neutron measurements in reactor physics and nuclear engineering with particular emphasis on neutron dosimetry in benchmark fields (see Matrix E706). 1.2 NRE are passive detectors and provide time integrated reaction rates. As a consequence, NRE provide fluence measurements without the need for time-dependent corrections, such as arise with radiometric (RM) dosimeters (see Test Method E1005). NRE provide permanent records, so that optical microscopy observations can be carried out anytime after exposure. If necessary, NRE measurements can be repeated at any time to examine questionable data or to obtain refined results. 1.3 Since NRE measurements are conducted with optical micro......

Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry

ANSI C63.7-2005 进行辐射测量的露天测试点的施工指南

Information that is useful in constructing an open-area test site (OATS) used to perform radiated emission measurements in the frequency range of 3--1000 MHz is provided. Final validity of the test site can only be made by performing site attenuation mea

Guide for Construction of Open-Area Test Sites for Performing Radiated Emission Measurement

KS A ISO/ASTM 51275:2005 放射性铬薄膜剂量测定系统使用规程

이 규격은 수중에서 광자나 전자에 의해 조사된 물질의 흡수 선량을 측정하는 라디오크로믹 필

Practice for use of a radiochromic film dosimetry system

KS A ISO/ASTM 51400:2005 高剂量照射剂量测定校准实验室的特征和性能规程

이 규격은 감마선, 전자빔 또는 X-선(제동 복사) 등과 같은 전리 방사선을 포함한 선량

Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory

KS C IEC 61562:2005 辐射防护仪器.测量粮食中β.辐射放射性核素的比活度用的便携设备

이 규격은 식품에 함유되는 베타 방출 방사성 핵종의 비방사능 측정에 사용되며 현장 조건에서

Radiation protection instrumentation－Portable equipment for measuring specific activity of beta-emitting radionuclides in foodstuffs

KS C IEC 61256:2005 辐射防护仪表.洗衣房放射污染监测用监测仪

이 규격은 세탁물의 방사능 오염 감시에 사용되는 장치에 관해서 규정한다. 이 규격은 의류를

Radiation protection instrumentation－Installed monitors for the detection of radioactive contamination of laundry

ISO 21909:2005 无源专用中子剂量计.性能和试验要求

This International Standard provides performance and test requirements for determining the acceptability of personal neutron dosemeters to be used for the measurement of personal dose equivalent, Hp(10), for neutrons ranging in energy from thermal to 20 MeV.

Passive personal neutron dosemeters - Performance and test requirements

ISO/ASTM 51650:2005 醋酸纤维素剂量测定系统使用规程

1 This practice covers procedures for using the cellulose triacetate (CTA) dosimetry system for measuring absorbed dose and dose profile in materials irradiated by electrons and photons in terms of absorbed dose to water. The CTA dosimeter is a routine dosimeter especially useful for measurement of dose distribution. Note 1—Cellulose triacetate dosimeter refers to untinted film dosim-eter. 2 This practice applies provided the following conditions are satisfied. 2.1 The absorbed-dose range is 10 kGy to 300 kGy for electrons and photons. 2.2 The absorbed-dose rate range is 3 Gy/s to 4×10 Gy/s (1). 2.3 The radiation-energy range for electrons is 0.2 to 50 MeV. 2.4 The radiation-energy range for photons is 0.1 to 50 MeV. 2.5 The irradiation-temperature range of the dosimeter is -10 to 70℃. 3 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. note: 2 The boldface numbers in parentheses refer to the list of references at the end of this standard.

Practice for use of a cellulose triacetate dosimetry system

ISO/ASTM 51649:2005 在300 keV 和25 MeV 能量之间辐射加工用电子束设备中剂量测定的实施规程

1 This practice covers dosimetric procedures to be fol-lowed in Installation Qualification, Operational Qualification and Performance Qualifications (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed. Note 1—For guidance in the selection and calibration of dosimeters, see ISO/ASTM Guide 51261. For further guidance in the use of specific dosimetry systems, and interpretation of the measured absorbed dose in the product, also see ISO/ASTM Practices 51275, 51276, 51431, 51607, 51631, 51650, and 51956. For use with electron energies above 5 MeV, see Practice E 1026, and ISO/ASTM Practices 51205, 51401, 51538, and 51540 for discussions of specific large volume dosimeters. For discussion of radiation dosimetry for pulsed radiation, see ICRU Report 34. 2 The electron beam energy range covered in this practice is between 300 keV and 25 MeV, although there are some discussions for other energies. 3 Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other measures besides dosimetry may be required for specific applications such as medical device sterilization and food preservation. 4 Other specific ISO and ASTM standards exist for the irradiation of food and the radiation sterilization of health care products. For food irradiation, see ISO/ASTM Practice 51431. For the radiation sterilization of health care products, see ISO 11137. In those areas covered by ISO 11137, that standard takes precedence. 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 appro-priate safety and health practices and determine the applica-bility of regulatory requirements prior to use.

Practice for dosimetry in an electron beam facility for radiation processing at energies between 300 keV and 25 MeV

ISO/ASTM 51956:2005 辐射加工用热致发光剂量测定(TLD)系统使用规程

1 This practice covers procedures for the use of thermolu-minescence dosimeters (TLDs) to determine the absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. 2 This practice covers systems that permit absorbed dose measurements under the following conditions: 2.1 The absorbed-dose range is from 1 Gy to 100 kGy. 2.2 The absorbed-dose rate is between 1 × 10 and 1 × 10 Gy s. 2.3 The radiation-energy range for photons and electrons is from 0.1 to 50 MeV. 3 Absorbed dose and absorbed-dose rate measurements in materials subjected to neutron irradiation are not covered in this practice. 4 Procedures for the use of TLDs for determining ab-sorbed dose in radiation-hardness testing of electronic devices are given in ASTM Practice E 668. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for use of thermoluminescence dosimetry (TLD) systems for radiation processing

ISO/ASTM 51608:2005 辐射加工用X射线(韧致辐射)设备中放射剂量测定实施规程

1 This practice outlines the installation qualification pro-gram for an X-ray (bremsstrahlung) irradiator and the dosim-etric procedures to be followed during operational qualifica-tion, performance qualification and routine processing to ensure that the entire product has been treated within a predetermined range of absorbed dose. Other procedures re-lated to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits and energy limits for X-radiation is not within the scope of this practice. 2 In contrast to monoenergetic gamma radiation, the bremsstrahlung energy spectrum extends from low values (about 35 keV) up to the maximum energy of the electrons incident on the X-ray target (see Section 5 and Annex AI). 3 Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other controls besides dosimetry may be required for specific applications, such as medical device sterilization and food preservation. 4 For the irradiation of food and the radiation sterilization of health care products, other specific ISO standards exist. For food irradiation, see ISO/ASTM Practice 51431. For the radiation sterilization of health care products, see ISO 11137. In those areas covered by ISO/ASTM Practice 51431 or ISO 11137, those standards take precedence. Note 1—For guidance in the selection, calibration, and use of specific dosimeters and interpretation of absorbed dose in the product from dose measurements, see the documents listed in Section 2. Note 2—Bremsstrahlung characteristics are similar to those of gamma radiation from radioactive nuclides. See ISO/ASTM Practices 51204 and 51702 for the applications of dosimetry in the characterization and operation of gamma irradiation facilities. For information concerning electron beam irradiation technology and dosimetry, see ISO/ASTM Practices 51431 and 51649. 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.

Practice for dosimetry in an X-ray (Bremsstrahlung) facility for radiation processing

ISO/ASTM 51707:2005 辐射加工的剂量测定中不确定度的估算指南

1 This guide defines possible sources of uncertainty in dosimetry performed in gamma, X-ray (bremsstrah)ung), and electron irradiation facilities and offers procedures for estimat-ing the resulting magnitude of the uncertainties in the mea-surement of absorbed dose using a dosimetry system. Basic concepts of measurement, estimate of the measured value of a quantity, "true value", error, and uncertainty are defined and discussed. Components of uncertainty are discussed and meth-ods are given for evaluating and estimating their values. How these contribute to the standard uncertainty in the reported values of absorbed dose are considered and methods are given for calculating the combined standard uncertainty and an estimate of expanded (overall) uncertainty. The methodology for evaluating components of uncertainty follows ISO proce-dures (see 2.3). The traditional concepts of precision and bias are not used in this document. Examples are given in five annexes. 2 This guide assumes a working knowledge of statistics. Several statistical texts are included in the references (1-4). 3 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this guide.

Guide for estimating uncertainties in dosimetry for radiation processing

ISO/ASTM 51539:2005 辐射敏感性指示计使用指南

1 This guide covers procedures for using radiation-sensitive indicators (referred to hereafter as indicators) in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation (1-5). 2 The purpose for using indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels. 3 Indicators are not dosimeters and shall not be used as a substitute for proper dosimetry. Information about dosimetry systems for radiation processing is provided in other ASTM and ISO/ASTM documents (see ISO/ASTM Guide 51261). 4 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 appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. note: 2 The boldface numbers in parentheses refer to the bibliography at the end of this guide.

Guide for use of radiation-sensitive indicators