共找到 281 条与 核仪器与核探测器综合 相关的标准,共 19 页
Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory
Practice for use of a radiochromic optical waveguide dosimetry system
Practice for use of a polymethylmethacrylate dosimetry system
Practice for use of a radiochromic film dosimetry system
Practice for use of a ceric-cerous sulfate dosimetry system
Practice for dosimetry in an electron-beam facility for radiation processing at energies between 300 keV and 25 MeV
Practice for use of cellulose acetate dosimetry system
Practice for dosimetry in a gamma irradiation facility for radiation processing
Nuclear - Used Underwater Lighting Assembly
Electrotechnical vocabulary. Chapter 394 : nuclear instrumentation : instruments.
This International Standard applies to containers of liquid, solid or gaseous samples for use with cooled germanium detectors in quantitative gamma-ray measurements. The container volumes range from 50 cm to 3 000 cm. The purpose of this standard is to specify the volume, the dimensions and the physical characteristics of the containers used in routine gamma-ray spectrometry of liquid, solid, or gaseous samples. This standard combined with IEC 60937 and IEC 60973 defines a limited number of source-detector geometries which are useful in inter-laboratory comparisons, particularly in the field of radiological protection. The use of uniform sample containers will facilitate the reproducibility of counting and the determination of efficiency curves in addition to making such efficiency curves more universally useful from laboratory to laboratory. Reproducibility of the defined geometries should be ensured by suitable measures (use of centering devices, for example) that are not part of the present standard. This standard is particularly applicable to semiconductor gamma-ray detectors but can also be used with scintillation detectors.
Nuclear instrumentation - Sample containers for gamma-ray spectrometry with Ge-detectors
Radiation protection instrumentation - Measurement of personal dose equivalents Hp(10) and Hp(0,07) for X, gamma and beta radiations - Direct reading personal dose equivalent and/or dose equivalent rate dosemeters
General specifications for packaging of nuclear instrumentation products
Nomenclature for the type of nuclear radiation detectors
General safety requirements for nuclear instrumentation
Electrotechnical vocabulary. Chapter 393 : nuclear instrumentation : physical phenomena and basic concepts.
1.1 This practice covers procedures for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in the beltline of light-water cooled nuclear power reactor vessels. This practice includes guidelines for designing a minimum surveillance program, selecting materials, and evaluating test results. 1.2 This practice was developed for all light-water cooled nuclear power reactor vessels for which the predicted maximum neutron fluence ( > 1 MeV) at the end of the design lifetime exceeds 1 X 10 17 n/cm (1 X 10 21 n/m ) at the inside surface of the reactor vessel. 1.3 This practice does not provide procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program.
Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)
1.1 This test method describes procedures for measuring reaction rates and fast-neutron fluences by the activation reaction 32S(n,p)32P.1.2 This activation reaction is useful for measuring neutrons with energies above approximately 3 MeV.1.3 With suitable techniques, fission-neutron fluences from about 5 108 to 1016 n/cm 2 can be measured.1.4 Detailed procedures for other fast-neutron detectors are described in Practice E 261.1.5 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 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
1.1 This test method describes procedures for measuring reaction rates and fast-neutron fluences by the activation reaction 32 S(n,p) 32 P. 1.2 This activation reaction is useful for measuring neutrons with energies above approximately 3 MeV. 1.3 With suitable techniques, fission-neutron fluences from about 5 X 10 to 10 16 n/cm can be measured. 1.4 Detailed procedures for other fast-neutron detectors are described in Practice E261. 1.5 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 Test Method for Measuring Reaction Rates and Fast-Neutron Fluences by Radioactivation of Sulfur-32
Graphical symbols, writing abbreviations and parameter symbols for nuclear instruments
Copyright ©2007-2022 ANTPEDIA, All Rights Reserved
京ICP备07018254号 京公网安备1101085018 电信与信息服务业务经营许可证:京ICP证110310号