Academic literature on the topic 'Feedbacks radioactifs'
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Journal articles on the topic "Feedbacks radioactifs"
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Voss, R. "Radioactive and kinematic tracers of feedback from massive stars." EPJ Web of Conferences 19 (2012): 10004. http://dx.doi.org/10.1051/epjconf/20121910004.
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Iwata, Ren, Shigeki Yamazaki, and Tatsuo Ido. "Automated injection of a radioactive sample for preparative HPLC with feedback control." International Journal of Radiation Applications and Instrumentation. Part A. Applied Radiation and Isotopes 41, no. 12 (1990): 1225–27. http://dx.doi.org/10.1016/0883-2889(90)90211-x.
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Pysklywec, Russell N., and Christopher Beaumont. "Intraplate tectonics: feedback between radioactive thermal weakening and crustal deformation driven by mantle lithosphere instabilities." Earth and Planetary Science Letters 221, no. 1-4 (2004): 275–92. http://dx.doi.org/10.1016/s0012-821x(04)00098-6.
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Peng, Tianlin, Dewen Tang, and Jianing Wu. "Design of an autonomous navigation system for emergency disposal robots at radioactive waste sites under extreme climatic conditions." Journal of Physics: Conference Series 2419, no. 1 (2023): 012088. http://dx.doi.org/10.1088/1742-6596/2419/1/012088.
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Abstract There are many factors of environmental hazards that endanger the lives of personnel at radioactive waste sites after sudden extreme weather disasters, and the use of robotic substitutes can effectively safeguard the lives of personnel. For the situation where the environmental information of radioactive waste sites is unknown and there are many variables, an autonomous navigation system of emergency disposal robots with strong resilience and stability is designed. First, an algorithm based on the Rao-Blackwellized particle filtering theory is used in the autonomous navigation system to achieve more accurate robot positioning and map building through four processes: prediction, correction, resampling, and map building. Second, the traditional path planning algorithm combined with road information is added to Hopfield neural network to achieve deep analysis of complex road conditions. Finally, the intelligent voice interaction function is added to the navigation system to realize the robot’s interaction and real-time monitoring and feedback. The experimental results show that the emergency disposal robot has high accuracy in positioning, navigation, obstacle avoidance, etc., can respond quickly in unexpected situations and can carry out effective voice interaction.
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Huang, Hanzhi. "Current status and applications of time-to-digital converters." Applied and Computational Engineering 53, no. 1 (2024): 79–83. http://dx.doi.org/10.54254/2755-2721/53/20241275.
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Time-to-Digital Converter (TDC) is widely used to realize time interval measurement. The high-precision time measurement technique has important applications in the fields of laser ranging, particle identification, and radioactive nuclear medicine engineering. Based on the existing literature research and data, this paper studies the application areas of TDC in the present development and analyzes the future prospects of TDC applications. The research results showed that: TDC, based on signal screening, realizes time interval measurement as the ultimate purpose of building the system and, at the same time, completes the function of multi-pulse time interval measurement, which can meet the needs of more diversified measurements in the experiments. In the circuit structure, it can identify the feedback output in the all-digital phase-locked loop (ADPLL) and the reference clock phase and frequency information between the feedback output and the reference clock in an ADPLL. It is also promising for use in other areas of high-precision time measurement and processing of circuit signals.
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Lin, Xiaofeng, Shoujun Zhou, Tiexiang Wen, Shenghao Jiang, Cheng Wang, and Jingtao Chen. "A novel multi-DoF surgical robotic system for brachytherapy on liver tumor: Design and control." International Journal of Computer Assisted Radiology and Surgery 16, no. 6 (2021): 1003–14. http://dx.doi.org/10.1007/s11548-021-02380-7.
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Abstract Purpose Radioactive seed implantation is an effective invasive treatment method for malignant liver tumors in hepatocellular carcinomas. However, challenges of the manual procedure may degrade the efficacy of the technique, such as the high accuracy requirement and radiation exposure to the surgeons. This paper aims to develop a robotic system and its control methods for assisting surgeons on the treatment. Method We present an interventional robotic system, which consists of a 5 Degree-of-Freedom (DoF) positioning robotic arm (a 3-DoF translational joint and a 2-DoF revolute joint) and a needle actuator used for needle insertion and radioactive seeds implantation. Control strategy is designed for the system to ensure the safety of the motion. In the designed framework, an artificial potential field (APF)-based motion planning and an ultrasound (US) image-based contacting methods are proposed for the control. Result Experiments were performed to evaluate position and orientation accuracy as well as validate the motion planning procedure of the system. The mean and standard deviation of targeting error is 0.69 mm and 0.33 mm, respectively. Needle placement accuracy is 1.10 mm by mean. The feasibility of the control strategy, including path planning and the contacting methods, is demonstrated by simulation and experiments based on an abdominal phantom. Conclusion This paper presents a robotic system with force and US image feedback in assisting surgeons performing brachytherapy on liver tumors. The proposed robotic system is capable of executing an accurate needle insertion task with by optical tracking. The proposed methods improve the safety of the robot’s motion and automate the process of US probe contacting under the feedback of US-image.
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Pan, Lung-Fa, Chao-Yu Chiang, Chao-Chun Huang, et al. "Thyroid Biokinetics for Radioactive I-131 in Twelve Thyroid Cancer Patients via the Refined Nine-Compartmental Model." Applied Sciences 12, no. 11 (2022): 5538. http://dx.doi.org/10.3390/app12115538.
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The thyroid biokinetic model of radioactive I-131 was re-evaluated using a refined nine-compartmental model and applied to twelve thyroid cancer patients. In contrast to the simplified four-compartmental model regulated by the ICRP-56 report, the revised model included nine compartments specified in the ICRP-128 report, namely, oral, stomach, body fluid, thyroid, whole body, liver, kidney, bladder, and remainder (i.e., the whole body minus kidney and bladder). A self-developed program run in MATLAB was designed to solve the nine first-order simultaneous linear differential equations. The model was realized in standard and simplified versions. The latter neglected two feedback paths (body fluid to oral, i31, and kidney to the whole body, i87) to reduce computations. Accordingly, the biological half-lives for the major compartments (thyroid and body fluid + whole body) were 36.00 ± 15.01, 15.04 ± 5.63, 34.33 ± 15.42, and 14.83 ± 5.91 of standard and simplified version. The correlations between theoretical and empirical data for each patient were quantified by the dimensionless AT (agreement) index and, the ATtot index integrated each individual AT of a specific organ of one patient. Since small AT values indicated a closer correlation, the obtained range of ATtot (0.048 ± 0.019) proved the standard model’s reliability and high accuracy, while the simplified one yielded slightly higher ATtot (0.058 ± 0.023). The detailed outcomes among various compartments of twelve patients were calculated and compared with other researchers’ work. The correlation results on radioactive I-131 evolution in thyroid cancer patients’ bodies are instrumental in viewpoint of radioactive protection of patients and radiological personnel.
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Wissmeier, Laurin, and Joachim Poppei. "Simulating the feedback between corrosive gas generation and water availability for the evaluation of radionuclide mobility in the context of radioactive waste disposal." Safety of Nuclear Waste Disposal 1 (November 10, 2021): 109–10. http://dx.doi.org/10.5194/sand-1-109-2021.
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Abstract. It has been recently recognized that the availability of liquid water may be a controlling factor in the feedback between the physical processes of variably saturated liquid and gas flow on the one hand, and various chemical processes such as metal corrosion in an underground storage facility for radioactive waste on the other hand (e.g., Huang et al., 2021, and reference therein). Iron corrosion in anoxic conditions produces hydrogen gas and consumes water, as expressed by the following stylized chemical equation (e.g., Diercks and Kassner, 1988; Senior et al., 2021): 3Fe+4H2O⟶Fe3O4+4H2 Since water is an educt the corrosion reaction may be suspended or suppressed by the scarcity of water near the corroding surfaces. At the same time, gas pressure build-up through hydrogen generation may limit further water ingress. We developed a model that focuses on the close coupling between gas generation through iron corrosion and water availability. The feedback between iron corrosion, gas generation and liquid phase flow is considered by implementing the corrosion reaction in the subsurface flow and transport simulator PFLOTRAN (Hammond et al., 2012; Lichtner et al., 2015, 2020) making use of its coding provisions to implement source/sink terms for water and gas. These source/sink terms reflect the kinetics of the iron corrosion and its dependence on the educts, where the availability of water is approximated by the local liquid saturation. The model was applied to evaluate the mobility of radionuclides in, and their release from a hypothetical geological storage facility for radioactive waste. The radionuclides are traced through the emplacement chambers and drift by means of advective and diffusive transport. Parameter variations illustrate the influence of crucial modelling parameters on the simulation results.
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Васин, М., M. Vasin, В. Соловьев, et al. "Primary Radiation Stress, Inflammatory Reaction and the Mechanism of Early Postradiation Reparative Processes in Irradiated Tissues." Medical Radiology and radiation safety 63, no. 6 (2018): 71–81. http://dx.doi.org/10.12737/article_5c0eb50d2316f4.12478307.
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The products of radiolysis released from cellular compartment under the influence of ionizing radiation: highly mobile groups of proteins, damaged nuclear and mitochondrial DNA, extracellular ATP and oxidized low density lipoproteins, cause stress activation in irradiated tissues through a pattern of the receptors with start of the cascade r53 and NF-κB of pro-inflammatory ways conducting to an expression of pro-inflammatory genes stimulating synthesis of cytokines of the IL-1 family. Excessive activation of pro-inflammatory way under the influence of a radioactive stress is limited to synthesis, anti-inflammatory cytokines: IL-4, IL-10, IL-11, IL-13 and also antagonists of IL-1 receptor and TGF-β. G-CSF and MG-CSF induced by action of pro-inflammatory cytokines have anti-inflammatory and anti-apoptotic properties decreasing level of pro-inflammatory cytokines IL-6 and TNF. Glucocorticoids participate in regulation of primary radioactive stress, suppressing an excessive expression of genes of pro-inflammatory cytokines. Increased IL-1 level stimulates secretion of corticosteroids through mechanism of feedback. Adrenergic stimulation is capable to raise a gene IL-1β expression. The mechanism of radiation apoptosis of stem cells is implemented through p53-Puma way which blocks interaction anti-apoptotic proteins of Bcl-2 with pro-apoptotic proteins of Bax and Bak. After release from mitochondrion of cytochrome C and apoptosis-inducing factor there is an activation of effector caspases: caspases 3, 6 and 7 through caspase 9, and final cell destruction. Wnt way is crucial for post-radiation repair. Potential of the regenerative response of hemopoietic tissue to radiation injury depends on catenin and ability of Wnt way to stimulate post-radiation bone marrow reparation. Mesenchymal stem cells of bone marrow play a large role in post-radiation regeneration of hemopoietic tissue. Their main action is carried out through TLR2 and TLR4 receptors. Mobilization of hemopoietic stem cells is bound to release proteases from bone marrow, including neutrophil elastase and cathepsin G, and a matrix metalproteinase-9. Radioprotective properties of exogenous IL-1 aren’t limited only by induction of raised G-CSF and GM-CSF production. The larger role in radiation protection is played by the reaction induced by IL-1 in the form of feedback with production anti-apoptotic and anti-inflammatory factors. Primary radioactive stress limits time of radiomitigable effect of IL-1 by 1-2 h after its application after radiation.
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Stevanović, Jelenka Savković. "Ecosystem Energy Changes." International Journal of Research and Scientific Innovation X, no. XII (2024): 267–75. http://dx.doi.org/10.51244/ijrsi.2023.1012022.
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In this paper energy in ecosystem was studied. Energy balance equations of ecosystem were derived. Most of the energy in the Earth’s system comes from just a few sources: solar energy, gravity, radioactive decay, and the rotation of the earth. Earth is constantly changing as energy flows through the system. Earth’s weather and climate are mostly driven by energy from the Sun. The Sun provides the energy that drives the water cycle on Earth. In this paper different forms of energy, specific types, using and energy conservation were studied. Environments are highly complex systems whose evolution is determined by complicated networks of positive and negative feedback loops. In this paper macroscopic and microscopic approaches to energy flow through the ecosystem have been used.
Dissertations / Theses on the topic "Feedbacks radioactifs"
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Albright, Anna Lea. "The trade-wind boundary layer and climate sensitivity." Electronic Thesis or Diss., Sorbonne université, 2022. http://www.theses.fr/2022SORUS207.
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La réponse des nuages des régimes d'alizés au réchauffement climatique reste incertaine. Elle soulève notamment la possibilité d'une sensibilité climatique élevée due à une diminution de la fraction nuageuse sous l'effet de l'interaction entre le mélange convectif, la turbulence, le rayonnement et l'environnement à grande échelle. La campagne EUREC4A (Elucidation du rôle du couplage nuage-circulation dans le climat) a apporté de nouvelles observations qui permettent de mieux comprendre la physique des régimes d'alizés, et d'apporter pour la première fois une contrainte sur la rétroaction des cumulus d'alizés basée sur les processus. Je montre d'abord comment les observations EUREC4A permettent d'approfondir la compréhension de la structure verticale caractéristique de la couche limite des alizés et des processus qui produisent cette structure. Elles amènent à revisiter certains aspects des modèles conceptuels et suggèrent un rôle plus actif des nuages dans le maintien de cette structure. Cette compréhension physique est ensuite appliquée à l'évaluation des rétroactions des cumulus d'alizés, montrant que les observations rendent peu plausibles les fortes rétroactions des cumulus d'alizés dans le réchauffement climatique<br>The response of trade-wind clouds to warming remains uncertain, raising the specter of a large climate sensitivity. Decreases in cloud fraction are thought to relate to interplay among convective mixing, turbulence, radiation, and the large-scale environment. The EUREC4A (Elucidating the role of cloud-circulation coupling in climate) field campaign made extensive measurements that allow for deeper physical understanding and the first process-based constraint on the trade cumulus feedback.I first use EUREC4A observations to improve understanding of the characteristic vertical structure of the trade-wind boundary layer and the processes that produce this structure. This improved physical understanding is then applied to the evaluation of trade cumulus feedbacks. Ideas developed support new conceptual models of the structure of the trade-wind boundary layer and a more active role of clouds in maintaining this structure, and show little evidence for a strong trade cumulus feedback to warming
Book chapters on the topic "Feedbacks radioactifs"
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Sert, Gilles, and Marie-Thérèse Caillard-Lizot. "Experience Feedback for Assessment of Transport Package Design Safety Reports." In Basics of Transport and Storage of Radioactive Materials. WORLD SCIENTIFIC, 2018. http://dx.doi.org/10.1142/9789813234048_0016.
Full textConference papers on the topic "Feedbacks radioactifs"
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Dutzer, Michel, Ge´rald Ouzounian, Roberto Miguez, and Jean-Louis Tison. "Radioactive Waste: Feedback of 40-Year Operations in France." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40081.
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France’s experience in the management of radioactive waste is supported by forty years of operational activities in the field of surface disposal. This feedback is related to three disposal facilities: Centre de la Manche disposal, not far away Cherbourg, from design to post-closure facility. Centre at Soulaines-Dhuys from site selection to design to operation during nearly 20 years. Centre at Morvilliers from site selection to operation for seven years now. During the operational period of Centre de la Manche disposal facility (1969–1994), the safety concept for low- and intermediate level short lived waste (LIL-SLW) was developed and progressively incorporated in the procedures of the facility. The facility entered its institutional control period and the experience of this facility has been useful for the operating facilities. Centre de l’Aube that took over Centre de la Manche, and Morvilliers for very low level wastes. Both facilities currently accommodate the major part of the volume of radioactive wastes that are generated in France. However disposal facilities have to be considered as rare resources. Then new waste management options are being investigated as the disposal of large components or recycling metallic wastes within the nuclear industry.
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Kreitman, Paul J., Joseph Boucau, Per Segerud, and Stefan Fallstro¨m. "Feedback From Westinghouse Experience on Segmentation of Reactor Vessel Internals." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59013.
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With more than 25 years of experience in the development of reactor vessel internals segmentation and packaging technology, Westinghouse has accumulated significant know-how in the reactor dismantling market. Building on tooling concepts and cutting methodologies developed decades ago for the successful removal of nuclear fuel from the damaged Three Mile Island Unit 2 reactor (TMI-2), Westinghouse has continuously improved its approach to internals segmentation and packaging by incorporating lessons learned and best practices into each successive project. Westinghouse has developed several concepts to dismantle reactor internals based on safe and reliable techniques, including plasma arc cutting (PAC), abrasive waterjet cutting (AWJC), metal disintegration machining (MDM), or mechanical cutting. Westinghouse has applied its technology to all types of reactors covering Pressurized Water Reactors (PWR’s), Boiling Water Reactors (BWR’s), Gas Cooled Reactors (GCR’s) and sodium reactors. The primary challenges of a segmentation and packaging project are to separate the highly activated materials from the less-activated materials and package them into appropriate containers for disposal. Since space is almost always a limiting factor it is therefore important to plan and optimize the available room in the segmentation areas. The choice of the optimum cutting technology is important for a successful project implementation and depends on some specific constraints like disposal costs, project schedule, available areas or safety. Detailed 3-D modeling is the basis for tooling design and provides invaluable support in determining the optimum strategy for component cutting and disposal in waste containers, taking account of the radiological and packaging constraints. Westinghouse has also developed a variety of special handling tools, support fixtures, service bridges, water filtration systems, video-monitoring systems and customized rigging, all of which are required for a successful reactor vessel internals segmentation and packaging project. The purpose of this paper is to provide an overview of the Westinghouse reactor internals segmentation experience by illustrating projects related to various types of reactors and providing feedback from project execution.
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Faucheux, Claire, and Nicolas Jeanne´e. "Industrial Experience Feedback of a Geostatistical Estimation of Contaminated Soil Volumes." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59181.
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Geostatistics meets a growing interest for the remediation forecast of potentially contaminated sites, by providing adapted methods to perform both chemical and radiological pollution mapping, to estimate contaminated volumes, potentially integrating auxiliary information, and to set up adaptive sampling strategies. As part of demonstration studies carried out for GeoSiPol (Geostatistics for Polluted Sites), geostatistics has been applied for the detailed diagnosis of a former oil depot in France. The ability within the geostatistical framework to generate pessimistic / probable / optimistic scenarios for the contaminated volumes allows a quantification of the risks associated to the remediation process: e.g. the financial risk to excavate clean soils, the sanitary risk to leave contaminated soils in place. After a first mapping, an iterative approach leads to collect additional samples in areas previously identified as highly uncertain. Estimated volumes are then updated and compared to the volumes actually excavated. This benchmarking therefore provides a practical feedback on the performance of the geostatistical methodology.
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Guiberteau, Philippe, and Jean-Guy Nokhamzon. "French Alternative Energies and Atomic Energy Commission Decommissioning Programme and Feedback Experience." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96016.
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Since the French Atomic Energy Commission (CEA) was founded in 1945 to carry out research programs on use of nuclear, and its application France has set up and run various types of installations : research or prototypes reactors, process study or examination laboratories, pilot installations, accelerators, nuclear power plants and processing facilities. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R&D facilities in line with the issues of the nuclear industry of the future. Since the 1960s and 1970s in all its centers, the CEA has acquired experience and know-how through dismantling various nuclear facilities. The dismantling techniques are nowadays operational, even if sometimes certain specific developments are necessary to reduce the cost of operations. Thanks to availability of techniques and guarantees of dismantling program financing now from two dedicated funds, close to 15 B€ for the next thirty years, for current or projected dismantling operations, the CEA’s Nuclear Energy Division has been able to develop, when necessary, its immediate dismantling strategy. Currently, nearly thirty facilities are being dismantled by the CEA’s Nuclear Energy Division operational units with its industrial partners. Thus the next decade will see completion of the dismantling and radioactive clean-up of the Grenoble site and of the facilities on the Fontenay-aux-Roses site. By 2018, the dismantling of the UP1 plant at Marcoule, the largest dismantling work in France, will be well advanced, with all the process equipment dismantled. After an overview of the French regulatory framework, the paper will describe the DD&R strategy, programme and feedback experience inside the CEA’s Nuclear Energy Division and its progress since ICEM 14 in 2011’s conference in Reims.
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Jeanjacques, Michel, Marie Pierre Bremond, Laurent Gautier, Guy Vieillard, David Estivie´, and Eric Pichereau. "Building 18: Operating Feedback From Cleaning and Dismantling of Glove Boxes and Shielding Lines." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16046.
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This summary presents the clean-up and dismantling works on glove boxes and shielded lines in building 18. The Atomic Energy Commission’s centre at Fontenay Aux Roses (CEA-FAR) was created in 1946. A radiochemical laboratory devoted to R&D programs focused on studies of irradiated fuel reprocessing processes, waste treatment processes and studies and production of transuranic elements was built in the early 1960s. The R&D program was finally halted on 30 June 1995. The purpose of the building 18 clean-up program is to minimise the nuclear and traditional hazards and to reduce as much as possible the production of high- and medium-level waste during subsequent dismantling work. The paper will deal with a short description of the operations as well as the lessons learned and the feedback experience which could be of any help in on going or planned DD&R projects.
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Cournoyer, Michael E., Steven Lee, and Robert F. Grundemann. "An Independent Analysis of a Glovebox Glove Failure Incident." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1133.
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Abstract As part of the “Lessons Learned” Program, a recent glovebox glove failure incident is examined to provide feedback and continuous improvement of the Safe Work Practices (SWPs) work-control process. While slowly evaporating liquid from solutions in trays on hot plates, a glovebox became pressurized and a glove ruptured resulting in widespread contamination of equipment, work surfaces, and the floor. Based on the post-analysis of the solution and residues of the incident, several contributing causes of the overpressurization were ruled-out, including exposure to strong shock, organic materials, and inorganic species. Evaporation of an ammonium nitrate solution was postulated as the cause of the incident glovebox breach. Since ceramic-top stirring hotplates heat from 150°C to 590°C and are controlled by a voltage power controller, the temperature to reach rapid decomposition conditions (210°C) was possible. The risk of these types of incidents is control to acceptable level by replacing voltage power controlled hotplates with temperature controlled ones. In addition, a still pot thermometer is required to prevent the solution from evaporating to dryness. Using a heating device designed such that 210°C cannot be reached under any circumstances further minimizes the risk. In summary, a primary objective of the Integrated Safety Management program is to minimize hazards associated with materials whenever possible. Implementing “Lessons Learned” not only maintains SWPs, but also contributes to an organization’s scientific and technological excellence. As with all other elements of business, there are costs associated with implementing an effective “Lessons Learned” Program. Using a cost-benefit analysis for another category of reportable occurrences, radiation exposure, it was estimated that over $50,000 could be spent on “Lessons Learned” to reduce the likelihood of this type of unusual occurrences and still be cost-effective. While the cost saving may not be immediately apparent, feedback in the form of incident reports provide continuous improvement in day-to-day operations.
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Yanagihara, Satoshi, Mitsuo Tachibana, Taro Shimada, Takenori Sukegawa, and Kunio Shiraishi. "Experience of Clean-Up Activities and Feedback to Future D&D Projects: Japan Power Demonstration Reactor Decommissioning Project." In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1225.
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Abstract In the Japan Power Demonstration Reactor (JPDR) decommissioning project, the procedure for clean-up activities was specially studied for harmonization with radioactive waste treatment policy in Japan; it consisted of several components such as survey of the facility operational history, radiological characterization of building surfaces, decontamination and final survey of radioactivities. After confirming that there was no significant radioactivity in the facilities in the final step of the procedure, buildings were demolished in consideration of treatment of wastes as non-radioactive materials. The JPDR decommissioning project was completed by March 1996 with no serious problems, which showed that the procedure was rational, and that the experiences are useful for planning of future decommissioning activities. The dismantling and clean-up activities were reviewed, and the experiences are excepted to contribute to establishing standard and regulatory systems on decommissioning nuclear facilities.
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Scelles, Fabien, Yves Kettering, and Frédérique Damerval. "Decommissioning of the MAU Facility at La Hague: How a Good Association of Milling Tools Can Facilitate the Decommissioning of Nuclear Areas?" In ASME 2023 International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2023. http://dx.doi.org/10.1115/icem2023-109961.
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Abstract It is often the case, in reprocessing facilities and waste repositories, that surface decontamination requires mechanical milling techniques on concrete, cement or brick surfaces (coated or uncoated). Integrated and compliant techniques for the efficient milling of these surfaces are in demand in a growing decommissioning sector, due to a large number of these scenarios which present challenging geometries. This is the case for the dismantling of the MAU building which is part of Orano La Hague’s UP2 400 fuel recycling plant. Mechanical processes proved to work since facilities are being decommissioned; however, the capability of such applications to fulfill the requirement in term of economics, techniques and environment/social need to be confirmed. Particularly, the speed rate, the strenuous working conditions, the dust’s capture’s efficiency, the possibility to obtain a final surface state that allows final surface radiological measurements have often been criticized in the various feedbacks from the work sites. To improve clean-up operations on dismantling sites, ORANO DS collaborated with the company Astillo. Specialized in the design and manufacture of machine and tool for the surface removal of pollutants, Astillo benefits from experience in the surface treatment’s sector. Particularly, the possibility to work with no detectable increase in airborne exposures (efficient vacuum attachments), the guarantee that all workers’ exposition to dose is kept as low as possible (semi-remote operation), the potential to accommodate a wide range of surfaces geometry and types by adaptable tools will be described.
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Lamotte, Hervé, Luc Torreblanca, and Suzel Vilarel. "Radioactive Waste Characterization and Tracking System at the French Atomic Energy Commission." In ASME 2013 15th International Conference on Environmental Remediation and Radioactive Waste Management. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icem2013-96057.
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CARAIBES is the traceability information system in radioactive solid waste management of the French Atomic Energy Commission, (CEA). Initially developed for the reprocessing facility of low and intermediate level waste of the centre of Cadarache, it has been gradually enhanced to manage very low level waste and the facilities of the centres of Saclay and Fontenay-aux-Roses. This software is directly connectable to characterization equipment as X-Ray measurement, gamma spectrometric measurement and/or neutronic measurement. After 15 years of operation, a new information system should replace it in 2014. This new CARAIBES V2 will make the functional and technical improvements resulting from the CARAIBES feedback but will also allow to manage all produced and/or treated waste in the Atomic Energy Commission and to ensure the traceability of waste and waste treatment before and after its packaging. From the analysis of the processes, waste management was described as an iterative process where, in every step, the facility in charge of a waste will apply a treatment to it (packaging, association or division) and will characterize it in order to evacuate it towards the next facility. Associated with a strongly customizable information system, this process allows the management of all kind of radioactive waste, including radioactive liquids. The final objectives are: to share a unique software and only one database for all CEA’s facilities involved in radioactive waste management, to be able to track the radioactive waste through all steps of its process, to meet the user’s needs as well as the regulatory requirements.
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Aubonnet, Emilie, and Didier Dubot. "Soils Radiological Characterization Under a Nuclear Facility." In ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2011. http://dx.doi.org/10.1115/icem2011-59046.
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Nowadays, nuclear industry is facing a crucial need in establishing radiological characterization for the appraisal and the monitoring of any remediation work. Regarding its experience in this domain, the French Alternative Energies and Atomic Energy Commission (CEA) of Fontenay-aux-Roses, established an important feedback and developed over the last 10 years a sound methodology for radiological characterization. This approach is based on several steps: - historical investigations; - assumption and confirmation of the contamination; - surface characterization; - in-depth characterization; - rehabilitation objectives; - remediation process. The amount of measures, samples and analysis is optimized for data processing using geostatistics. This approach is now used to characterize soils under facilities. The paper presents the radiological characterization of soils under a facility basement. This facility has been built after the first generation of nuclear facilities, replacing a plutonium facility which has been dismantled in 1960. The presentation details the different steps of radiological characterization from historical investigations to optimization of excavation depths, impact studies and contaminated volumes.