ASTM C1807-15
采用无源中子测量法对特种核材料 (SNM) 的滞留量进行无损分析的标准指南
Standard Guide for Nondestructive Assay of Special Nuclear Material (SNM) Holdup Using Passive Neutron Measurement Methods
ASTM C1807-15 发布历史
ASTM C1807-15由美国材料与试验协会 US-ASTM 发布于 2015。
ASTM C1807-15 发布之时，引用了标准
- ASTM C1009 核工业化学分析实验室制订质量保证计划的标准指南
- ASTM C1455 采用伽马射线光谱法对特种核材料的滞留量进行无损分析的标准试验方法
- ASTM C1490 无损检测（NDA）人员的选择、培训和资格鉴定标准指南
- ASTM C1592/C1592M 质量无损检测测量的标准指南
- ASTM C1673 C26.10无损试验方法的标准术语
ASTM C1807-15的历代版本如下：
- 2015年 ASTM C1807-15 采用无源中子测量法对特种核材料 (SNM) 的滞留量进行无损分析的标准指南
5.1 This guide assists in satisfying requirements in such areas as safeguards, SNM inventory control, nuclear criticality safety, waste disposal, and decontamination and decommissioning (D&D). This guide can apply to the measurement of holdup in process equipment or discrete items whose neutron production properties may be measured or estimated. These methods may meet target accuracy for items with complex distributions of SNM in the presence of moderators, absorbers, and neutron poisons; however, the results are subject to larger measurement uncertainties than measurements of less complex items.
5.2 Quantitative Measurements—These measurements result in quantification of the mass of SNM in the holdup. They include all the corrections and descriptive information, such as isotopic composition, that are available.
5.2.1 High-quality results require detailed knowledge of radiation sources and detectors, radiation transport, calibration, facility operations, and error analysis. Consultation with qualified NDA personnel is recommended (Guide C1490).
5.2.2 Holdup estimates for a single piece of process equipment or piping often include some compilation of multiple measurements. The holdup estimate must appropriately combine the results of each individual measurement. In addition, uncertainty estimates for each individual measurement must be made and appropriately combined.
5.3 Scan—Radiation scanning, typically gamma, may be used to provide a qualitative description of the extent, location, and the relative quantity of holdup. It can be used to plan or supplement the quantitative neutron measurements. Other indicators (for example, visual) may also indicate a need for a holdup measurement.
5.4 Nuclide Mapping—To appropriately interpret the neutron data, the specific neutron yield is needed. Isotopic measurements to determine the relative isotopic composition of the holdup at specific locations may be required, depending on the facility.
5.5 Spot Check and Verification Measurements—Periodic re-measurement of holdup at a defined point using the same technique and assumptions can be used to detect or track relative changes in the holdup quantity at that point over time. Either a qualitative or quantitative method can be used.
5.6 Indirect Measurements—Neutron measurements do not identify the radionuclide that produced the neutron signal. The specific neutron yield shall be determined independently of the neutron measurement.
5.7 Modeling—Modeling is recommended as an aid in the evaluation of complex measurement situations. Measurement data are used with a radiation transport model that includes a description of the physical location of equipment and materials. Because of the complexity of neutron transport calcu......
- 标准号
- ASTM C1807-15
- 发布
- 2015年
- 发布单位
- 美国材料与试验协会
- 当前最新
- ASTM C1807-15
- 引用标准
- ANSI N15.20 ASTM C1009 ASTM C1455 ASTM C1490 ASTM C1592/C1592M ASTM C1673