{"id":385653,"date":"2024-10-20T03:31:44","date_gmt":"2024-10-20T03:31:44","guid":{"rendered":"https:\/\/pdfstandards.shop\/product\/uncategorized\/bs-iso-244592021\/"},"modified":"2024-10-26T06:24:54","modified_gmt":"2024-10-26T06:24:54","slug":"bs-iso-244592021","status":"publish","type":"product","link":"https:\/\/pdfstandards.shop\/product\/publishers\/bsi\/bs-iso-244592021\/","title":{"rendered":"BS ISO 24459:2021"},"content":{"rendered":"
This document specifies a method for the determination of uranium concentrations in nitric acid or TBP-DILUANT (for example TBP-kerosene) solutions coming from the nuclear fuel cycle.<\/p>\n
The method is applicable<\/p>\n
for process control of solutions, free of suspension, which contain between 10 g\/l to 300 g\/l uranium, and<\/p>\n<\/li>\n
for high accuracy purposes (Safeguards) to nitric acid solutions, free of suspension, which contain between 100 g\/l and 220 g\/l uranium.<\/p>\n<\/li>\n<\/ul>\n
Having<\/p>\n
the content of neptunium and plutonium impurities in the solution less than 1 % of the uranium content.<\/p>\n<\/li>\n
the content of neutron poisons (gadolinium, erbium) less than 1 % of the uranium content to ensure the absence of significant interferences at the level of required precision, for high accuracy purposes.<\/p>\n<\/li>\n<\/ul>\n
The method is applicable to solid samples as well, provided that they can be fully dissolved in nitric acid.<\/p>\n
PDF Pages<\/th>\n | PDF Title<\/th>\n<\/tr>\n | ||||||
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2<\/td>\n | National foreword <\/td>\n<\/tr>\n | ||||||
6<\/td>\n | Foreword <\/td>\n<\/tr>\n | ||||||
7<\/td>\n | 1 Scope 2 Normative references 3 Terms and definitions 4 Principle <\/td>\n<\/tr>\n | ||||||
8<\/td>\n | 5 Reagents and materials 5.2 Uranium reference solutions. 6 Apparatus <\/td>\n<\/tr>\n | ||||||
9<\/td>\n | 6.1 X-ray tube. 6.2 Shielding and collimator. 6.3 Sample cell. <\/td>\n<\/tr>\n | ||||||
10<\/td>\n | 6.4 X-ray detector and multichannel analyser. 6.5 Software. 6.5.1 For data acquisition. 6.5.2 For data processing. 7 Method 7.1 Pre-checks 7.2 Reference spectrum 7.3 Calibration <\/td>\n<\/tr>\n | ||||||
11<\/td>\n | 7.4 Sample measurement 7.5 Spectrum evaluation 7.5.1 Region of interest 7.5.2 Smoothing (optional) <\/td>\n<\/tr>\n | ||||||
12<\/td>\n | 7.5.3 Background subtraction 7.5.4 Calculation of the X-ray transmission <\/td>\n<\/tr>\n | ||||||
13<\/td>\n | 7.6 Calculation of the concentration of uranium <\/td>\n<\/tr>\n | ||||||
14<\/td>\n | 7.7 Quality control 7.8 Uncertainty evaluation 7.8.1 Standard uncertainty of the calibration factor 7.8.2 Standard uncertainty of the uranium concentration <\/td>\n<\/tr>\n | ||||||
16<\/td>\n | Annex A (informative) Calculation method for correction factors of atomic mass and temperature <\/td>\n<\/tr>\n | ||||||
17<\/td>\n | Annex B (informative) Preparation of a solid quality control sample <\/td>\n<\/tr>\n | ||||||
19<\/td>\n | Bibliography <\/td>\n<\/tr>\n<\/table>\n","protected":false},"excerpt":{"rendered":" Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry<\/b><\/p>\n |