17.240;27.120.30 标准查询与下载

NF M60-351*NF EN ISO 19017:2017 放射性废物的γ能谱测量指南

Guidance for gamma spectrometry measurement of radioactive waste

ISO 21484:2017 核能. 燃料技术. 采用重量分析法测定MOX芯块的氧金属比

Nuclear Energy - Fuel technology - Determination of the O/M ratio in MOX pellets by the gravimetric method

ISO 19017:2015 放射性废物的γ能谱测量指南

Guidance for gamma spectrometry measurement of radioactive waste

ASTM E261-15 采用放射性技术测定中子的积分通量, 积分通量率和中子波谱的标准实施规程

5.1 Transmutation Processes—The effect on materials of bombardment by neutrons depends on the energy of the neutrons; therefore, it is important that the energy distribution of the neutron fluence, as well as the total fluence, be determined. 1.1 This practice describes procedures for the determination of neutron fluence rate, fluence, and energy spectra from the radioactivity that is induced in a detector specimen. 1.2 The practice is directed toward the determination of these quantities in connection with radiation effects on materials. 1.3 For application of these techniques to reactor vessel surveillance, see also Test Methods E1005. 1.4 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 appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Note 1: Detailed methods for individual detectors are given in the following ASTM test methods: E262, E263, E264, E265, E266, E343, E393, E481, E523, E526, E704, E705, and E854.

Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques

ASTM E265-15 通过硫-32的放射性测量反应速率和快速中子注量的标准试验方法

5.1 Refer to Guides E720 and E844 for the selection, irradiation, and quality control of neutron dosimeters. 5.2 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence and fluence rate with threshold detectors. 5.3 The activation reaction produces 32P, which decays by the emission of a single beta particle in 1008201;% of the decays, and which emits no gamma rays. The half life of 32P is 14.284 (36)3 days (1) 4 and the maximum beta energy is 1710.66 (21) keV (1). 5.4 Elemental sulfur is readily available in pure form and any trace contaminants present do not produce significant amounts of radioactivity. Natural sulfur, however, is composed of 32S (94.998201;% (26)), 34S (4.258201;% (24)) (2), and trace amounts of other sulfur isotopes. The presence of these other isotopes leads to several competing reactions that can interfere with the counting of the 1710-keV beta particle. This interference can usually be eliminated by the use of appropriate techniques, as discussed in Section 8. 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 58201;×8201;108 to 1016 n/cm 2 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

ASTM E481-15 通过钴和银的放射性测量中子注量率的标准试验方法

3.1 This test method uses one monitor (cobalt) with a nearly 1/v absorption cross-section curve and a second monitor (silver) with a large resonance peak so that its resonance integral is large compared to the thermal cross section. The pertinent data for these two reactions are given in Table 1. The equations are based on the Westcott formalism ((2, 3) and Practice E261) and determine a Westcott 2200 m/s neutron fluence rate nv0 and the Westcott epithermal index parameter . References 4, 5, and 6 contain a general discussion of the two-reaction test method. In this test method, the absolute activities of both cobalt and silver monitors are determined. This differs from the test method in the references wherein only one absolute activity is determined. (A) The numbers in parenthesis following given values are the uncertainty in the last digit(s) of the value; 0.729 (8) means 0.729 ± 0.008, 70.8(1) means 70.8 ± 0.1.(B) A 2200 m/s cross section (E = 0.0253 eV, T = 20°C) was taken from the sources indicated in Ref (9).(C) Cross section uncertainty data is taken from Ref (7) , the cross section comes from the other reference.(D) Calculated using Eq 10.(E) Cross section uncertainty comes from convariance data provided in the cross section source. The other reference indicates the source of the cross section.(F) In Fig. 1, Θ = 4ErkT/AΓ 2 = 0.2 corresponds to the value for 109Ag for T = 293 K, ∑r = N0σr, max. σr, max=29999 barn at 5.19 eV (

Standard Test Method for Measuring Neutron Fluence Rates by Radioactivation of Cobalt and Silver

NF M60-466:2009 核燃料技术.MOX球粒中的O/M比值的测定.重量法

Nuclear fuel technology - Determination of the O/M ratio in MOX pellets - Gravimetric method.

ISO 21484:2008 核燃料技术.MOX芯块中O/M比率的测定.重量分析法

Nuclear fuel technology - Determination of the O/M ratio in MOX pellets - Gravimetric method

NF M60-462-1*NF ISO 21847-1:2007 核燃料技术.α光谱测定法.第1部分:铀及其化合物中镎的测定

Nuclear fuel technology - Alpha spectrometry - Part 1 : determination of neptunium in uranium and its compounds.

NF M60-462-3*NF ISO 21847-3:2007 核燃料技术.α光谱测定法.第3部分:铀及其化合物中铀232的测定

Nuclear fuel technology - Alpha spectrometry - Part 3 : determination of uranium 232 in uranium and its compounds.

ISO 21847-1:2007 核燃料技术.α光谱测定法.第1部分:铀及其化合物中镎的测定

This part of ISO 21847 describes a method for determining trace amounts of 237Np in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 1: Determination of neptunium in uranium and its compounds

ISO 21847-3:2007 核燃料技术.α光谱测定法.第3部分:铀及其化合物中铀232的测定

This part of ISO 21847 describes a method for determining trace amounts of 232U in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 3: Determination of uranium 232 in uranium and its compounds

ISO 21847-2:2007 核燃料技术.α光谱测定法.第2部分:铀及其化合物中钚的测定

This part of ISO 21847 describes a method for determining trace amounts of 238Pu and 239Pu + 240Pu in uranium hexafluoride, uranium oxides or uranyl nitrate.

Nuclear fuel technology - Alpha spectrometry - Part 2: Determination of plutonium in uranium and its compounds