T/CIRA 46-2023 Active
T/CIRA 46-2023 Analyzing liquid scintillation method for strontium 89 and strontium 90 in liquid radioactive waste from nuclear power plants
Abstract
Main technical content: This document specifies the methodological principles, reagents and materials, instruments and equipment, samples, experimental steps, data processing, and test reports for analyzing the activity concentrations of strontium-89 and strontium-90 in liquid effluents from nuclear power plants. This document is applicable to the analysis of strontium-89 and strontium-90 in liquid effluents from nuclear power plants, and other nuclear reactor installations can refer to it for use. The lower limit of quantitative detection for strontium-89 in liquid effluents from nuclear power plants is 0.04 Bg/l, and the lower limit of quantitative detection for strontium-90 is 0.03 Bq/l.
General Product Information
| Document Type | Group standards |
|---|---|
| Standard Status | Active |
| Standard Code | T/CIRA 46-2023 |
| ICS | Fissile material |
| Implement Date | 2023-12-31 |