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By Bertrand Quiniou, Pierre Amadieu

Ion exchange technologies and processes are proven and established technologies widely used in numerous industries including hydrometallurgy for metal separation and recovery from metal bearing solutions. They have evolved through innovation which includes the development of countercurrent multistage (or multivessel) ion-exchange contactor systems with the benefit, for industrial operations, of greatly reduced footprints and ion-exchange media inventories, as compared to more traditional fixed bed contactor systems. Information on procedures for design and sizing of countercurrent multistage ion-exchange contactor systems is not readily available since it is most often proprietary know-how. The purpose of the present work is to develop a simple and innovative approach for the sizing and modeling of industrial countercurrent multistage ion-exchange contactor systems. The suggested approach builds upon published results and upon the following observation: in an industrial setting, knowledge of how component concentration or load on a contactor output streams vary with time t within a cycle duration (0 < t < T) is generally of little interest, only knowledge of time average of such concentration or load over a cycle duration T is sought for. The presented approach will be tested against current or past performances of industrial countercurrent multistage contactors of Orano Mining operations such as SNK‑3M moving packed bed contactors in Kazakhstan and NIMCIX fluidized bed contactors in Namibia.

Jan 1, 2020

By L. Shasko

Deliberative mapping is a method of public engagement designed to bring citizens and specialists together to inform policy decisions in conflict-laden areas of science and technology (Stirling and Davies 2004a). Citizens and specialists participate in the process both separately and together. A deliberative mapping study was held in Regina, Saskatchewan in October and November of 2019. Participants in the study assessed options for reducing greenhouse gas emissions in small, remote or off-grid communities, including assessing the role of small modular nuclear reactors (SMRs) in climate change mitigation. Deliberative mapping is designed to facilitate direct, two-way conversations between citizens and specialists through both formal and informal discussions. The relationship building component of this process may increase trust. Public consultation processes that lack two-way dialogue or are seen as obligatory rather than meaningful can worsen public opposition or lead to negative public perceptions. Public education alone is not enough to change public opinion. Providing people with more information on topics they already hold opinions on can work to reaffirm previously held biases, but building relationships can provide new pathways to overcome divisions and turn close-mindedness into open-mindedness.

Jan 1, 2020

By Mark Liskowich

When is it the proper time to initiate engagement with various stakeholders, including Indigenous communities? This paper will demonstrate what stage of a project’s evolution is the appropriate time to initiate a stakeholder engagement plan. It will look at aspects to consider when identifying the communities to involve. It will describe the contents of a Stakeholder Engagement Management Plan as well and touch on how tried and true options analyses, such as a Multiple Accounts Analysis can be used to inform the results of the engagement, guide the development of your project and clearly document the engagement process. It will illustrate the benefits of initiating engagement at the appropriate point in your project’s schedule, and the limitations of doing so too early and at later stages of the project engineering. The benefits of this approach can be realized within any legislative Jurisdiction including the Canadian Environmental Assessment Act 2012 and Canada’s new Impact Assessment Act.

Jan 1, 2020

By T. S. Grewal, S. C. Gupta, H. Natarajan, T. W. McQuade, N. Nejibulloev-Mamedov

Cigar Lake is one of the world’s largest high-grade uranium mines. The ore mined at Cigar Lake is milled at Orano Canada Inc’s (Orano) McClean Lake mill. The average Cigar Lake ore uranium grade since the start of mining activities in 2014 is 17.8% U (range 8– 28%). To achieve budgeted production of 18 M lbs U3O8/yr the required average feed tonnage to the mill is about 45 kt/yr. Arsenic, occurring as arsenides and sulpharsenides, is one of the major elements of concern associated with Cigar Lake ore. The leaching process is a sulphuric acid leach under oxidizing conditions at near atmospheric pressure. The presence of arsenic in the ore consumes oxidant in leaching as well as ferric sulphate in tailings preparation for arsenic sequestration. The average arsenic grade since the start of mining at Cigar Lake is 0.57% As. Further, the ore is hosted in a matrix of sandstone and clay, which results in poor settling in CCD. The average uranium grade for the balance of Cigar Lake Phase 1 ore is expected to drop to 12.5% U and the average arsenic grade is expected to increase to 1.6 % As, with an annual average peak of 2.5%. Therefore the tonnage throughput required to sustainably meet the production target will increase to 55 kt per year. Orano partnered with Hatch Ltd. (Hatch) to perform a gap analysis study to identify key circuits and equipment in the mill that would require debottlenecking. A METSIM mass balance model of the McClean Lake mill was generated and validated with actual mill operating data. Various feed scenarios were then studied, and the outcome was a traffic light table, which highlighted feed scenarios that exceeded installed capacity of major equipment and circuits. The results provided the basis for the PDC for the pre-feasibility study. This paper will outline the results of the gap analysis, the mass balance model, the feed scenarios and the study undertaken to prepare the McClean Lake mill for the change in ore quality from Cigar Lake.

Jan 1, 2020

By John R. Hayes, Kebbi A. Hughes, John Rowson, Peter E. R. Blanchard, Jeremiah C. Beam, Andrew P. Grosvenor, Arthur Situm

Uranium ore bodies contain elements within mineral phases that need to be disposed of responsibly. Solid waste can be placed in a tailings management facility (TMF) to contain the waste elements and limit interactions with the environment. It is important to understand how the chemistry of the tailings evolves throughout the lifetime of the operations that feed the TMF and after the site has been decommissioned. The objective of our collaboration with Orano Canada was to study how the tailings from the TMF located at McClean Lake, Saskatchewan change over time. This manuscript discusses our use of X-ray absorption spectroscopy (XAS) and X-ray microprobe to study the fate of Mo and Ca in the tailings. Mo is considered an element of concern (EOC) and it is necessary to determine if a stable solid Mo-bearing species forms. Thermodynamic modeling suggested that aqueous Mo would precipitate over time as powellite (CaMoO4). Comparing Mo K-edge XAS spectra from the solid tailings to the aqueous Mo concentration in the pore water showed that powellite did form and that this did result in a decrease in the aqueous Mo concentration over time. Further, it has been proposed that Ca2+(aq) can react with bicarbonate ions in the pore water and precipitate as calcium carbonate (e.g., CaCO3). This reaction would limit the aqueous bicarbonate present in the tailings that could react with uranyl ions to form soluble uranyl-carbonate complexes. We have identified several trace Ca-bearing species, including carbonates, in the tailings using XAS and X-ray microprobe.

Jan 1, 2020

By N. Chow, W. McCombe, G. Remple, J. Nikkari, L. Nightingale-Mercer

Orano Canada Inc. (Orano) operates the McClean Lake mill in northern Saskatchewan, processing high concentration uranium ore, delivered in slurry form, from the Cameco operated Cigar Lake mine. This slurry is ultimately processed into the purified uranium oxide product known as calcined yellowcake. During the calcining process, sulphate (SO42-) entrained in the yellowcake undergoes thermal decomposition into sulphur dioxide (SO2). SO2 is a colourless gas that poses health and safety risks. Since 2016, an anhydrous ammonia dosing system was successfully added to the existing Venturi particulate scrubber system to provide efficient removal of SO2 from the calciner off-gas. Within the pH controlled scrubber solution, SO2 exists in a pH dependent equilibrium with sulphite/bisulphite (SO32-/ HSO3-). The presence of a significant fraction of reduced sulphite and bisulphite in mill solutions presents a hazard in downstream circuits. Should these solutions drop in pH, either through natural oxidation or inadvertent mixing with low pH solutions, the solution equilibrium will shift from SO32-/HSO3- in favour of SO2, resulting in the evolution of SO2 gas from any liquid surfaces. In 2018, Hatch Ltd. (Hatch) and Orano implemented a design change in the calciner scrubber system. Blowdown from this system is now treated in an oxidation pre-step utilizing hydrogen peroxide (H2O2) and anhydrous ammonia (NH3) for pH control, in order to convert the residual sulphite/bisulphite present in solution to stable ammonium sulphate product. This paper will detail some of the challenges and actions undertaken to minimize SO2 risk, culminating in the recent introduction of a novel system designed to oxidize sulphite/bisulphite and prevent mobilization from the calciner scrubber solution into other mill areas where there is the potential for acidification and SO2 release.

Jan 1, 2020

By I. A. Menshikh, S. A. Kotov, N. L. Shinkarkin

All the cycle for conversion of natural and reprocessed uranium of ROSATOM’s “TVEL” Fuel Company is concentrated at the Siberian Chemical Plant. Conversion capacities are located on two sites, i.e. the Radiochemical Plant, which refines feedstock, and the Conversion Plant, which produces uranium oxides and uranium hexafluoride. Liquid radioactive waste arising in the process, after pretreatment, is transferred to a dedicated national operator for underground disposal. Environmental strategies pursued by the Fuel Company involve the introduction of process solutions intended to eliminate liquid radioactive waste and convert it into a solid phase. In the 5–7 years coming, work will be performed to refurbish and upgrade conversion facilities of the Siberian Chemical Plant that will principally change its radioactive waste management scheme. This paper describes the current waste management scheme and sets out planned schemes for management of natural and reprocessed uranium waste, which will be implemented in the refurbishment of conversion facilities of the Siberian Chemical Plant. The new technologies for the management of liquid radioactive waste from uranium conversion described in the present paper have an undeniable advantage over the current technology mainly due to significantly less environmental harm.

Jan 1, 2020

By W. McCombe, G. Remple, L. Nightingale-Mercer

The McClean Lake Mill is located approximately 850 kilometres north of Saskatoon, Saskatchewan, Canada, and is operated by Orano Canada Inc. (Orano). The mill was designed to process high grade uranium ores, and a multi-year expansion was completed in 2014 to increase its production capacity to 24 Mlbs U3O8 per annum. The mill also underwent various upgrades to allow it to safely transition from processing low grade ores to high grade ores from the nearby Cigar Lake Mine. During the metallurgical test work on the Cigar Lake ores, it was identified that some ore zones of the deposit have a propensity to generate hydrogen gas during acid leaching. Hydrogen is a volatile and explosive gas, which poses obvious safety concerns in the leaching circuit. Uranium processing is further complicated by the fact that an oxidant in the form of oxygen gas or hydrogen peroxide is required to regenerate iron in the leach, which further increases the risk posed by hydrogen gas. During 2013 Orano and its consultant Hatch designed and engineered several novel upgrades to the leaching circuit to mitigate the risk of hydrogen gas evolution in the process. Best in class technology was utilized in addition to control and operating strategy changes to ensure the leaching circuit could be safely operated with ores that evolve hydrogen gas. This paper reviews the design concepts and modifications implemented on this unique and challenging project, and also provides an update on the operational reality of hydrogen in the circuit gained through five years of operational experience with hydrogen evolving ores.

Jan 1, 2020

By John Rowson, Caitlin Brown, Kebbi Hughes, Joseph Esslifie-Dughan

The McClean Lake mill in northern Saskatchewan, Canada, is operated by Orano Canada Inc. and has been in production for the last 20 years. The tailings preparation process at the mill has been designed with decommissioning in mind, to produce tailings that are geochemically stable over the long-term within the site’s tailings management facility. Twenty years of study have contributed to a detailed understanding of geochemical and geotechnical properties of the McClean Lake tailings. Validation of the tailings properties has occurred through in-situ sampling campaigns conducted initially every year, and later every five years. Each sampling campaign has applied the same rigorous sampling procedure to provide data with useful correlations year over year. Each campaign result compares elements such as the inherent variability of the tailings, consolidation of the tailings and variations in the tailings placement methods. We will discuss lessons learned from seven sampling campaigns over 20 years and present data to show the reliable tracking of geochemical evolution of the in-situ tailings over time; providing opportunities for continuous improvements.

Jan 1, 2020

By Thom Mambe, Angelo Fernando

The objective of this work was to identify key parameters related to the reduction of the sulphur content in ammonium diuranate (ADU), and the identification of solid products being formed under various operating conditions. A laboratory-scale, continuous ADU precipitation circuit was assembled using a glass reactor vessel immersed in a temperature-controlled water bath. A pre-prepared uranium feed solution was fed continuously using a peristaltic pump. Anhydrous ammonia mixed with compressed air was metered and pumped using a double-headed peristaltic pump. An over-head mixer was used to keep the solids in suspension. The precipitated ADU slurry was removed from the reactor at the same flow rate as the feed solution. The slurry was sampled to generate ADU solids for chemical and physical analysis after four hours of continuous operation to ensure steady-state conditions. The following variables were studied to determine their influence on the sulphur content in the resulting ADU. (a) sulphate:uranium molar ratio in the reactor (1:1, 1:5, 1:10 and 1:20) (b) precipitation pH ( pH 6, 6.5, 6.9, 7.5 and 9) and (c) precipitation temperature (40C and 60C) A total of 18 tests covering the above parameters were conducted, and the results indicated that the sulphur content in the resulting solids was highly dependent on the reaction pH. Out of the pH levels tested, tests completed at pH 6.9 and 7.5 generated solids containing the lowest sulphur contents, between 0.5 to 1.5% S uranium basis (UB). The sulphur content in solids was found to vary linearly with the sulphate:uranium ratio in the feed solution, showing a statistically valid correlation. The impact of temperature was minor between 40°C and 60°C, with a slight advantage at higher temperatures. Tests at a sulphate:uranium ratio of 1:1 produced solids with the lowest sulphur contents. The influence of pH or temperature on sulphur content in solids was almost non-existent at this sulphate:uranium ratio. Precipitation pH is the major factor influencing ADU sulphur content, followed by the uranium to sulphate ratio.

Jan 1, 2020

By B. K. Ayres

Modern management of uranium mine or mill waste storage facilities (WSFs) often requires that they be remediated or decommissioned with a cover system. In addition to creating a self-sustaining landscape that supports the end land use, cover systems are intended to reduce long-term risks to human and ecological receptors from the stored waste to acceptable levels. The performance and longevity of a cover system will be strongly influenced by the features or shapes of the WSF final landform. Hence, cover systems and landforms must be thought of as an integrated design. Based on the author’s experience, the most important elements of the design process for maximizing the potential of WSF final landforms / cover systems being sustainable over the long term are noted in this manuscript. Several key items that must be considered and addressed during the planning phase of constructing a WSF final landform are also described. Various methods for monitoring performance of a WSF final landform are also reviewed. Key aspects associated with decommissioning a tailings WSF and waste rock pile at the former Cluff Lake uranium mine in northern Saskatchewan are included to illustrate many of the practical insights provided in this paper.

Jan 1, 2020

By Dale Verran, Jared Orynik, Chad Sorba, David Bronkhorst

Denison Mines Corp. (“Denison”) has a 90% interest in the Wheeler River Uranium Project (“Wheeler River”) located along the eastern edge of the Athabasca Basin in northern Saskatchewan between the Key Lake mill and the McArthur River uranium mine. The project is host to the high-grade Phoenix and Gryphon uranium deposits, discovered by Denison in 2008 and 2014 respectively, which include combined Indicated Mineral Resources of 132.1 million pounds U3O8 (1,809,000 tonnes at an average grade of 3.3% U3O8). The Pre-Feasibility Study (“PFS”), completed in accordance with NI 43-101 in September 2018, is highlighted by the selection of the In-Situ Recovery (“ISR”) mining method for the development of the Phoenix deposit, with an estimated average operating cost of $4.33 (US$3.33) per pound U3O8. Phoenix is the highest-grade undeveloped uranium deposit known globally, including Indicated Mineral Resources of 166,000 tonnes at 19.1% U3O8 for 70.2 million pounds U3O8. The paper aims to provide a summary of Wheeler River and an overview of the proposed development of the Phoenix and Gryphon deposits according to the PFS completed for the Project. Further details regarding the PFS, including additional scientific and technical information are described in greater detail in the NI 43-101 Technical Report titled "Pre-Feasibility Study for the Wheeler River Uranium Project, Saskatchewan, Canada" dated October 30, 2018 with an effective date of September 24, 2018. A copy of this report is available on Denison's website and under its profile on SEDAR at www.sedar.com and on EDGAR at www.sec.gov/edgar.shtml.

Jan 1, 2020

By David Sanscartier, Elizaveta Petelina, Alexey Klyashtorin

This paper provides an overview of the radiological risk mitigation approach applied by the Saskatchewan Research Council (SRC) for the remediation of 35 legacy uranium mine sites in northern Saskatchewan where uranium exploration and extraction took place in the 1950–60s. Mining activities resulted in an irregular increase of the gamma radiation dose rate (up to 18 μSv/h). The radiological objectives for the sites include a gamma dose rate at a spot (<2.5 μSv/h above local background), and the dose rate averaged over a hectare (<1 μSv/h above local background). These objectives are generally achievable at the impacted sites through the installation of shielding soil cover. This method may be impractical for site areas with rough terrain (e.g., steep slopes) and/or difficult access. A risk assessment approach is applied to determine if these areas can be safely left uncovered or if additional mitigation measures should be implemented. The risk assessment approach is based on two factors: (i) the ambient radiation dose rates collected through gamma surveys, and (ii) actual land use data collected through various surveys of activities of local community members at the sites. Exposure scenarios based on four land uses are applied to estimate a potential annual dose load for members of the public. The estimated doses are compared with the criterion of 0.3 mSv/a recommended by the Canadian Guidelines for the Management of Naturally Occurring Radioactive Materials (NORM). If the criteria are not satisfied, a mitigation plan is developed, and post-remediation gamma levels are modelled using GIS tools to evaluate the performance of the proposed mitigations. The proposed approach allows the team to optimize resources for the site remediation so that public exposure to NORM are as low as reasonably achievable after remediation.

Jan 1, 2020

By D. Kong, A. Klyashtorin, L. McGilp, I. Wilson

This work reports on applying iron oxide coated sands media in an experimental permeable reactive barrier to remove uranium species from uranium containing water. A field experiment was conducted at the legacy Gunnar uranium mine & mill site that was abandoned in the 1960s with limited to no decommissioning. The flooded Gunnar mine pit presently contains about 3.2 million m3 of water contaminated by dissolved U (1.2 mg/l), Ra-226 (0.4 Bq/l), and minor concentrations of other contaminants (As, Se, etc.). The water is seeping over the pit rim into Lake Athabasca posing environmental and health concerns. Iron oxide coated sands can be used to immobilize uranium species through an adsorption process. Methods for preparation of hydrous ferric oxide sorbents and their supported forms onto silica sands are described. Fourier transform infrared spectroscopy (FTIR), and powder X-ray diffraction (pXRD) were used to characterize the physical-chemical properties of the sorbent. The monolayer uranium uptake capacity (Qm) was estimated through the Langmuir adsorption isotherm. Adsorption kinetic experiments were performed in a lab environment before moving to a field trial. Based on these lab results and the input on field-scale appropriate geometries, a pilot permeable reactive barrier was fabricated and a field test conducted near the Gunnar pit in June 2019. This pilot test provided technical data and information needed for designing a full-scale permeable barrier based on the iron oxide coated sands, which may be applied for in-situ water treatment at Gunnar and other legacy uranium sites.

Jan 1, 2020

By Sean Hillacre, Arthur Lieu

NexGen’s approach to uranium processing design including the crushing/grinding and leaching of raw ore through to yellowcake precipitation and tailings management focuses on minimizing surface footprint, freshwater consumption, and human radiation exposure. Applying the concept of best available technologies economically achievable (“BATEA”), NexGen continues to research, evaluate, test and validate various advanced technologies that can be incorporated into the Project design, including distinctive tailings storage techniques. Additionally, NexGen is proposing that tailings generated from the mill processes be used as cemented paste backfill of stopes, as well as stored in a purpose-built, Underground Tailings Management Facility (“UGTMF”) comprised of several dedicated chambers. The paste backfill method of tailings storage is used globally, however, constructing purpose-built tailings chambers in waste rock is a new concept in uranium mining, which would typically be cost prohibitive for most projects given the expense to develop non-economic material for the sole purpose of storing tailings. The Rook I Project is uniquely positioned to implement the UGTMF due to robust Project economics and favourable technical setting which provides NexGen with the opportunity to set an elite standard for tailings management. When compared to conventional surface tailings management facilities, storing tailings underground as cemented paste reduces geotechnical, geochemical, environmental, and human health risks associated with tailings management. Additionally, the UGTMF vastly reduces the area of surface disturbance and allows for progressive decommissioning during the life of mine operations.

Jan 1, 2020

By Meifeng Zhi, Yuqing Niu, Xixin Chang, Fengqi Zhao, Weimin Qiu, Hao Wang, Zhenqian Wen, Zujun Shu

An applicable Eluex process was developed for acid in-situ leaching (ISL) uranium mine in Bayanwula. In this process, uranium was adsorbed with strong base anion resin from the pregnant solution, then the loaded resin was eluted by sulfuric acid. After D2EHPA extraction, the concentrated eluate was enriched, and the loaded organic phase was stripped by sodium carbonate. The yellow cake was obtained by sodium hydroxide precipitation at last. The uranium concentration in the loaded strip solution was 52.8 g/L. Parameters of the process were determined, and the impact of the Eluex process in underground leaching was also investigated. In industrial design, 95% of raffinate went back to elution and 5% back to in-situ leaching. No significant effect on uranium leaching or resin adsorption was found.

Jan 1, 2020

By B. Pewkliang, K. Ehrig, E. Macmillan, M. Smith, V. Liebezeit, Y. Li

The Olympic Dam iron-oxide copper-gold (IOCG) uranium-silver deposit is the largest publicly declared uranium, fifth largest copper and third largest gold resource. Currently, the operation consists of an underground mine and integrated processing plant. Uranium is produced from leaching of flotation tailings and is a co-product to copper cathode with by-product gold and silver bullion. The Olympic Dam geometallurgy team began studying ore from the Southern Mine Area (SMA) in 2006 and soon discovered uranium behaviour was far more variable than the behaviour in the Northern Mine Area, which had been mined from the start of the operation in 1988. The primary objective of Olympic Dam geometallurgy is to develop metallurgical performance predictors that reliably describe the process performance of different ore types and distribute these into the resource block model for use as a fundamental input into mine planning. The nature of the uranium mineralisation (compositionally and texturally complex and highly variable) meant that classic mineralogy techniques alone could not provide the resolution required for prediction of uranium extraction. However, the combination of quantitative mineralogy, results from laboratory-scale leach tests and modelling within the geometallurgy program has enabled prediction of both uranium flotation recovery (via association with sulphides) and uranium leach extraction, including at variable leach conditions. These stope-based predictions have supported trade-off decisions between operating costs and uranium revenue, and have predicted the changing recovery as the mining operations have moved into the Southern Mine Area in recent years.

Jan 1, 2020

By W. L. Dam

Grand Junction, Colorado’s legacy with uranium mining and milling serves as a model attracting international interest. Access to water and central location to carnotite ore containing uranium and vanadium resulted in the World War II military creating a site in Grand Junction for developing extraction techniques; subsequently, several commercial mill sites were built in the area. Uranium mills produced ore into the 1970’s as well as tonnes of radioactive waste tailings. Tailings contain radium that emits radon gas. Despite the radiation hazard, sandy tailings were added to concrete and became incorporated into roads, schools, businesses and homes. Clean up of sites containing tailings and mill sites began in the 1970’s involving city, state, and federal officials. The Climax mill site had become an auto junk yard mixed with mill tailings. A new disposal site was built out of town and away from the river in the 1990’s. After Climax mill tailings were removed to the disposal site, the land sat vacant for two decades until citizens and city officials developed a masterplan for the riverfront property. The Las Colonias river park is being built in stages including an amphitheater, gardens, businesses and parks. One of the biggest obstacles to site remediation and reuse was overcoming public outrage, fear, and lack of trust which made funding sources scarce.

Jan 1, 2020

By Troy Boisjoli

Since its discovery in February 2014, the Arrow Uranium Deposit has undergone rapid development through aggressive and systematic drilling programs and is now being progressed through advanced engineering and permitting. Based on the 2018 NI 43-101 Technical Report, the Probable Mineral Reserve estimate totals 234.1 million (“M”) pounds (“lbs”) triuranium octoxide (“U3O8”), contained in 3.43 M tonnes at an average grade of 3.09% U3O8. The proposed processing plant at the Rook I Project (the “Project”) will be capable of producing up to 31 M lbs of U3O8 per year, with a projected mine life of nine years based on the Probable Mineral Reserve estimate, although NexGen is permitting a 24-year operating life at the Project assuming the majority of Inferred Mineral Resources are upgraded to Indicated Mineral Resources with continued mineral resource development drilling. The Project will be developed through transverse and longitudinal longhole mining methods, pairing primary and secondary stoping techniques with a high degree of equipment mechanization which will provide a combination of good productivity, high extraction, and stable back support. This next generation of uranium operations combines the use of advanced tele-remote equipment and instrumentation with a low-cost bulk mining method and a best-in-class tailings management practice, effectively reducing operating costs and setting a new standard for elite environmental and social practices.

Jan 1, 2020

By Hervé Toubon, Matthieu Davrinche, Jim Corman, Mamane Bello Boubacar Kinassa, Pierre Amadieu

Orano Mining maintains a significant level of Innovation and Development Research for its sites in Canada, Niger, Kazakhstan, Mongolia, and France. This effort is formalized within the six major thematic programs below, which include more than one hundred affiliated R&D projects:  Geological understanding, tools and methods for exploration  ISR technology (geology, modeling, mining development tools)  Mining technology (SABRE)  Ore treatment and processing (in particular via our Centre for Innovation for extractive metallurgy, CIME)  Environment (radiochemistry, modeling, tools and methods for remediation)  Digital Mine (sensors, transmission, database, and data modeling) This paper describes the main actions of these six programs, their stakes, and their progress. There is no single path leading to innovation but fostering an innovative context and a structured project approach are essential ingredients to successful development and industrial deployment. As a result, Orano Mining has, over the years, developed a disciplined methodology for R&D portfolio and project management. This methodology, presented here, targets a reduction in time to implementation while valuing both the expertise and the work in project mode.

Jan 1, 2020