Design of an unattended ore grading measurement system in a uranium mine
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Cong Chen
,
Weihua Zeng
,
Shengli Hou
Abstract
The unattended ore grading radioactivity measurement system is an important part of the digital uranium mine. However, with the promotion of the digitization of mines, the radioactivity measurement system for the truck checkpoint used to measure the grade of ore for hydrometallurgical process still maintains the backward processing method of offline measurement and manual recording. To improve the situation, an unattended ore grading measurement system using gamma detectors is developed. Through unattended identification, weighting and radioactivity measurement, the values of the grade of ore and the uranium content are calculated and uploaded automatically. The system has been put into practical use at a uranium mine in southern China in September 2021. Through the field use, the system can realize automatic measurement, reduce labor costs, and establish a production database, which lays the foundation for further application in the construction of digital mines on a large scale.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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© 2022 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
