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GB/T 11842-2025: Determination of oxygen to uranium atomic ratio in uranium dioxide powder and pellets - Thermogravimetric method
Status: Valid GB/T 11842: Evolution and historical versions
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| GB/T 11842-2025 | English | 219 |
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Determination of oxygen to uranium atomic ratio in uranium dioxide powder and pellets - Thermogravimetric method
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GB/T 11842-2025
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| GB/T 11842-1989 | English | 179 |
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Determination of oxygen to uranium atomic ratic in uranium dioxide powder and pellets by thermogravimetric method
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GB/T 11842-1989
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PDF similar to GB/T 11842-2025
Standard similar to GB/T 11842-2025 GB/T 10266 GB/T 11846 GB/T 11844 Basic data | Standard ID | GB/T 11842-2025 (GB/T11842-2025) | | Description (Translated English) | Determination of oxygen to uranium atomic ratio in uranium dioxide powder and pellets - Thermogravimetric method | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F46 | | Classification of International Standard | 27.120.30 | | Word Count Estimation | 10,157 | | Date of Issue | 2025-04-25 | | Date of Implementation | 2025-08-01 | | Older Standard (superseded by this standard) | GB/T 11842-1989 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 11842-2025: Determination of oxygen to uranium atomic ratio in uranium dioxide powder and pellets - Thermogravimetric method
---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
ICS 27.120.30
CCSF46
National Standard of the People's Republic of China
Replaces GB 11842-1989
Determination of oxygen-uranium atomic ratio in uranium dioxide powder and pellets
Released on 2025-04-25
2025-08-01 Implementation
State Administration for Market Regulation
The National Standardization Administration issued
Foreword
This document is in accordance with the provisions of GB/T 1.1-2020 "Guidelines for standardization work Part 1.Structure and drafting rules for standardization documents"
Drafting.
This document replaces GB 11842-1989 "Determination of oxygen-uranium atomic ratio of uranium dioxide powder and pellets by thermogravimetric method" and is consistent with GB 11842-
Compared with 1989, in addition to structural adjustments and editorial changes, the main technical changes are as follows.
a) The test device has been changed (see Chapter 5, Chapter 7, Chapter 3 and Chapter 4 of the 1989 edition);
b) The oxidation temperature has been changed (see Chapter 4, 7.2 and 7.4, 2.2 and 4.4.1 of the 1989 edition);
c) The sample weight has been changed (see 7.1, 4.1.2 of the 1989 edition);
d) The use of protective gas has been deleted (see 4.2 and 4.3.3 of the 1989 edition);
e) The test steps have been changed (see 7.2, 7.3 and 7.4, 4.2, 4.3 and 4.4 of the 1989 edition);
f) The form of the result calculation formula has been changed (see 8.1, Chapter 5 of the 1989 edition);
g) The method for correcting sample mass for volatile impurities has been changed (see 8.1, 8.4, and 4.3.4 of the 1989 edition);
h) Added the calculation method of uranium content (see 8.2).
Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents.
This document was proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).
This document was drafted by. China Nuclear Power Research and Design Institute, China Nuclear Jianzhong Nuclear Fuel Element Co., Ltd., China Nuclear 404 Co., Ltd.,
Nuclear Industry Standardization Institute.
The main drafters of this document are. Wang Guohua, Tang Wenlei, Yang Chaoping, Yu Jiamin, Lian Haoxiang, Li Yi, Li Bo, Zheng Na, Guo Jinxuan, An Shenping,
Ning Wei, Zhao Feng, Qiao Hongbo, Huang Yi, Chen Huihui, Li Yanping, Chen Cheng, Zhao Suyu.
The previous versions of this document and the documents it replaces are as follows.
---First published in 1989 as GB 11842-1989;
---This is the first revision.
Determination of oxygen-uranium atomic ratio in uranium dioxide powder and pellets
Thermogravimetry
1 Scope
This document specifies the principle, instrumentation, samples, test procedures, and methods for determining the oxygen-uranium atomic ratio of uranium dioxide powder and pellets by thermogravimetric method.
Experimental data processing and precision, etc.
This document applies to the determination of the oxygen-uranium atomic ratio of uranium dioxide powder and pellets, and the determination of uranium content in uranium dioxide powder and pellets.
Use as directed.
2 Normative references
This document has no normative references.
3 Terms and definitions
There are no terms or definitions that require definition in this document.
4 Principles of the method
The uranium dioxide powder and pellet samples were fully oxidized at 900℃±50℃ in air atmosphere to generate stable product uranium trioxide.
By measuring the mass of the sample before and after oxidation and deducting the impurity content, the oxygen-uranium atomic ratio and uranium content are calculated.
5.Instruments and Equipment
5.1 Muffle furnace. The operating temperature range is from room temperature to 1000℃, the temperature control accuracy is ±2℃, and the furnace atmosphere is air.
5.2 Electronic balance. graduation value 0.1 mg.
5.3 Dryer (including desiccant).
5.4 Crucible, made of platinum.
6 Samples
The sample is dry uranium dioxide powder or pellets stored in a desiccator.
7 Test steps
7.1 Take out the empty crucible that has been burned to constant weight at 900℃±50℃ from the desiccator and weigh the mass m0 of the crucible to an accuracy of 0.1 mg.
Weigh 5g~12g of uranium dioxide powder or pellet sample and place it in a crucible. The total mass of the sample and crucible is recorded as m1, accurate to 0.1mg.
7.2 For uranium dioxide powder samples, place the crucible containing the powder in a muffle furnace and raise the temperature of the muffle furnace to 900°C ± 50°C.
3h; For uranium dioxide pellet samples, place the crucible containing the pellets in a muffle furnace, raise the temperature of the muffle furnace to 500℃±50℃, and keep it warm for 3 hours.
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