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Relevant bibliographies by topics / Material nuclear sau radioactiv

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Academic literature on the topic 'Material nuclear sau radioactiv'

Author: Grafiati

Published: 2 June 2025

Last updated: 31 July 2025

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Journal articles on the topic "Material nuclear sau radioactiv"

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Alina, NITREAN. "CRIMINALISTICA NUCLEARĂ: INOVAȚIE ȘI COOPERARE GLOBALĂ." LEGEA ŞI VIAŢA=LAW AND LIFE=ЗАКОН И ЖИЗНЬ . 1, no. 381 (2025): 192–210. https://doi.org/10.5281/zenodo.15552931.

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Criminalistica nucleară reprezintă un domeniu inovator ce se bazează pe aplicarea tehnologiilor avansate și expertizei interdisciplinare în vederea prevenirii și combaterii infracțiunilor ce implică materiale nucleare sau radioactive. Acest domeniu este strâns legat de colaborarea internațională, care joacă un rol esențial în combaterea provocărilor ce depășesc granițele naționale. Inițiativele ITWG, GICNT și CBRN CoE, alături de organizații internaționale precum INTERPOL, IAEA și UNICRI, contribuie la consolidarea capacității statelor în domeniul criminalisticii nuclea

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Ergüler, Erol, and Necdet A. Bekir. "Nuclear Dacryocystography." European Journal of Therapeutics 4, no. 2 (1993): 298–304. http://dx.doi.org/10.58600/eurjther-199342-1113-x.

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Tears formed by the lacrimal glands that constantly bathe the delicate corneal tissue. Blockage of the normal pathway of drainage of tears from the eye into the nose and resultant epiphora (tearing) is a fairly common ophthalmologic problem. By placing a dorp of radioactive material in to the conjunctival sac, it is posibble to image the flow of tears through lacrimal drainage apparatus using gamına camera. Radionudide Dacryocystography provides a simple, accurate means for diagnosis or exduding obstructive changes in the lacrimal apparatus. in the physiological assesment of tearing problems,

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Yun, Ye-Sol, Kwang-Deok Choi, Nam-Kyun Kim, and Jong-Do Kim. "Removal Characteristics of Ni-Ferrite Oxide Film Formed on the Stainless Steel Surface in Fiber Laser Decontamination." Science of Advanced Materials 16, no. 2 (2024): 292–98. http://dx.doi.org/10.1166/sam.2024.4647.

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Every nuclear facility has a limited operating life, at the end of which they must be shut down and decommissioned. For decommissioning, the removal of radioactive contaminants and demolition should be considered. Before nuclear power plants are decommissioned, the primary system, which is the most heavily contaminated, is decontaminated first, followed by decontamination of the surfaces of containment containers and buildings. This study examined the removal characteristics of Ni-ferrite coated on the stainless steel (STS304) specimen surface using an eco-friendly laser that generates little

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Nishimura, T. "Interpretation of changing pore pressure on heated unsaturated/saturated bentonite-sand mixture." IOP Conference Series: Earth and Environmental Science 1124, no. 1 (2023): 012112. http://dx.doi.org/10.1088/1755-1315/1124/1/012112.

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Abstract Generation of electricity in nuclear power plants have supply further energy to society in the world, and remain arising of radioactive waste as results of performance industry with activity. Radioactive waste has to be isolated from the human habitat for absolutely so long time period until its radioactivity has decayed to an innocuous situation. To end disposal completely, every country operated Nuclear Energy plant foresees further deep geological repository. This study focused on couple phenomena associate to THMC properties for bentonite-sand mixture that particularly, soil moist

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D’Onorio, Matteo, Tommaso Glingler, Maria Teresa Porfiri, et al. "Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation." Energies 16, no. 3 (2023): 1149. http://dx.doi.org/10.3390/en16031149.

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The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, the complexity of the plant, and the presence of massive energy sources require a rigorous safety approach to fully realize fusion power’s environmental advantages. The Tokamak building barrier design must address two main issues: radioactive mass transport hazards and ener

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Xu, Xingang, Haifeng Bi, Yang Yu, et al. "Low leaching characteristics and encapsulation mechanism of Cs+ and Sr2+ from SAC matrix with radioactive IER." Journal of Nuclear Materials 544 (February 2021): 152701. http://dx.doi.org/10.1016/j.jnucmat.2020.152701.

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Lee, Ki Rak, Brian J. Riley, Hwan-Seo Park, et al. "Investigation of physical and chemical properties for upgraded SAP (SiO2Al2O3P2O5) waste form to immobilize radioactive waste salt." Journal of Nuclear Materials 515 (March 2019): 382–91. http://dx.doi.org/10.1016/j.jnucmat.2019.01.004.

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Feng, X., J. K. Bates, C. R. Bradley, and E. C. Buck. "Does Fully Radioactive Glass Behave Differently than Simulated Waste Glass?" MRS Proceedings 294 (January 1, 1992). http://dx.doi.org/10.1557/proc-294-207.

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ABSTRACTStatic tests at SA/V (ratio of surface area of glass to solution volume) 20,000 m−1 on SRL 200 glass compositions show that, at long test periods, the simulated nuclear waste glass (nonradioactive) leaches faster than the corresponding radioactive glass by a factor of about 40, although comparative tests, done through 560 days, at lower SA/V, 2000 m−1, indicate little difference in the leach behavior of the two types of glasses. The similarity in leach behavior between radioactive and simulated glasses at SAN of 2000 m−1 or lower is also observed for SRL 165/42 and 131/11 compositions.

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Books on the topic "Material nuclear sau radioactiv"

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Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management (2000 San Diego, Calif.). Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, California, June 4-8, 2000. American Nuclear Society, 2000.

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Book chapters on the topic "Material nuclear sau radioactiv"

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Goldstein, Inge F., and Martin Goldstein. "Radon In Your Basement." In How Much Risk? Oxford University Press, 2002. http://dx.doi.org/10.1093/oso/9780195139945.003.0008.

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We once saw a science fiction movie in which a monster from outer space is first detected because it sets Geiger counters clicking furiously. We were reminded of that movie by the story of how radon in homes first came to wide public attention. A nuclear power plant was built in a town in Pennsylvania, and like all such plants was equipped with radiation detectors, both to protect the health of employees and to prevent anyone from removing nuclear fuel from the plant. A newly employed engineer at the plant registered a high radioactivity when he walked by the detectors. This was not only alarm

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Chouhan, Er R. K., and Manish Mudgal. "Novel Radiation Shielding Concrete Utilizing Industrial Waste for Gamma-Ray Shielding." In Smart Materials Design for Electromagnetic Interference Shielding Applications. BENTHAM SCIENCE PUBLISHERS, 2022. http://dx.doi.org/10.2174/9789815036428122010015.

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For the first time, the capability of red mud waste has been explored for the development of advanced synthetic radiation shielding aggregate and radiation shielding concrete. Red mud, an aluminium industry waste, consists of multi.component and multi-elemental characteristics. Approximately two tons of red mud are generated for every ton of aluminium production. There are about 85 alumina plants all over the world, thus leading to the generation of about 77 million tons of highly alkaline waste annually. The major mineral content of red mud waste includes hematite, anatase, and cancrinite, th

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Conference papers on the topic "Material nuclear sau radioactiv"

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Li, Junfeng, and Jianlong Wang. "Cementation of Radioactive Waste Resin by Calcium Sulfoaluminate Cement." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75197.

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Spent radioactive ion-exchange resin (SIER) is a long-standing issue for radioactive waste management safety. Performance of radioactive waste form is featured with extra long-term and non-repairable. Calcium sulfoaluminate cement (SAC) was used in radioactive spent resins solidification in China. A prescription of X SAC cement + 0.5X waste resins (50%water hold) + 0.35X water was obtained first. In order to control the temperature rise caused by hydration of cement in 200L solidification matrix, various supplementary materials were tried. Based on compressive strength tests and center tempera

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Liu, Yu, Jing Liu, Cong Wang, and Heng Gao. "Study on Potential Leakage and Electrical Performance for Electrical Penetration Assemblies Under Severe Accident Conditions." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-64368.

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Abstract EPAs are the penetrations used to minimize leakage and supply instrumentation or power cables path. Hence, sealing performance of EPA is important to contain radioactive materials and minimize their release without any filtration. Leakage behavior of containment under SAC is also required for the evaluation of mitigation strategies, risk analysis, PSA and emergency planning. In addition, electrical continuity for EPA cables is important for the operation of mitigation systems under different conditions, especially the SAC. In this paper, it is focused on the review and study on leakag

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Sun, Qina, Junfeng Li, Jianlong Wang, Shixi Ouyang, Qiang Li, and Minghui Wu. "Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-30154.

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To investigate the solidification efficiency of sulfoaluminate cement (SAC) and to provide more information for formula optimization, SAC blending zeolite, accelerator and Dura fiber was used as matrix materials for solidification of simulated radioactive borate liquid waste. The simulated radioactive borate liquid waste was prepared with boric acid and sodium hydroxide using drinking water. The performances of solidified waste forms were evaluated mainly basing on matrix compressive strength and leachability. The 28d compressive strength of the solidified waste forms were tested according to

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Zhang, Naizhe, Weishuai Wang, Zhen Gao, Hai Liu, and Xuegang Liu. "Application of Plasma Arc Cutting Technology in Dismantling of Large Metal Components in Containment Building." In 2024 31st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/icone31-135612.

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Abstract The decommissioning of nuclear reactor is a challenge to the sustainable development of nuclear energy. One of the most challenging tasks in reactor decommissioning is the dismantling and segmentation of radioactive large metal components in the containment building. A variety of cutting technologies have been developed for the special purpose. This paper is focused on the underwater plasma arc cutting technology and its potential applications. The characteristics of large metal components in nuclear containment building were summarized. The matters needing attention in the process of

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Lewis, Donald Wayne. "Developing a Standard Code for Spent Fuel and High Level Waste Containment Baskets." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48285.

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ASME Section III, Division 3, “Containments for Transportation and Storage of Spent Nuclear Fuel and High Level Radioactive Material and Waste” currently addresses the design of transportation and storage containment shells but it has yet to address the containment internal support structure that holds the spent fuel or high level waste in place. However, the code for internal support structures, hereafter referred to by its common name “basket”, has been under development by ASME for the past 2 years. Development of the new code, to be known as Subsection WD, “Internal Support Structures” was

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Sanders, M. J., H. Jeanes, S. Fray, and H. U. Arnold. "Deployment of the RASP System for Cutting a Contaminated Power Reactor Turbine Shaft." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4860.

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A need was identified for the in-situ size reduction of large components such as glove boxes, tanks and other components. A development programme resulted in a new cutting method that could be remotely deployed for the in-situ segmentation of large components of this type. RWE NUKEM has selected RASP as acronym for this technology Remotely-Operated Advanced Segmentation Process or RASP. A review of the standard manual cutting methods highlighted a number of significant shortcomings including operative safety; high energy cutting tools generating high temperatures; spread of contamination over

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Pillokat, Peter, and Jan Hendrik Bruhn. "Experience in Dismantling and Packaging of Pressure Vessel and Core Internals." In ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2010. http://dx.doi.org/10.1115/icem2010-40036.

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Nuclear Company AREVA is proud to look back on versatile experience in successfully dismantling nuclear components. After performing several minor dismantling projects and studies for nuclear power plants, AREVA completed the order for dismantling of all remaining Reactor Pressure Vessel internals at German Boiling Water Reactor Wuergassen NPP in October ’08. During the onsite activities about 121 tons of steel were successfully cut and packed under water into 200l- drums, as the dismantling was performed partly in situ and partly in an underwater working tank. AREVA deployed a variety of diff

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Menon, Shankar, Bo Wirendal, Jan Bjerler, and Lucien Teunckens. "Validation of Dose Calculation Codes for Clearance." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4667.

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All proposals for clearance from regulatory control of very low level radioactive material are based on predicted scenarios for subsequent utilisation of the released materials. The calculation models used in these scenarios tend to utilise conservative data regarding exposure times and dose uptake as well as other assumptions as a safeguard against uncertainties. Another aspects is common to all these calculation models and codes: none of them has ever been validated by comparison with the actual real life practice of recycling. An international project has recently been concluded where two c

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Cantrel, Eric, Luc Denissen, Henri Davain, Jean-Phillipe Leveau, Johan Lauwers, and Thierry Gillet. "An Optimized Strategy for the Management of Spent Steam Generators." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7330.

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The decommissioning of the BR3 (Belgian Reactor 3) approaches its final phase. The electro-mechanical dismantling is almost completed and the program related to the decontamination of the building structures has been initiated. The issue of the evacuation of the primary circuit large components, and more specifically of the Steam Generator (SG), has been dealt successfully, applying innovative technologies to lead to remarkable results in terms of waste volume minimization and occupational radiation exposure. The strategy applied for the evacuation of the BR3 SG resulted from the elaboration a

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Carénini, L., and F. Fichot. "The Impact of Transient Behavior of Corium in the Lower Head of a Reactor Vessel for In-Vessel Melt Retention Strategies." In 2016 24th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2016. http://dx.doi.org/10.1115/icone24-60598.

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One of the main goals of severe accident management strategies is to mitigate radiological releases to people and environment. To choose the most appropriate strategy, one needs to know the probability of its success taking into account the associated uncertainties. In the field of corium and debris behavior and coolability, research programs are still on going and the possibilities to efficiently cool and retain corium and debris inside the Reactor Pressure Vessel (RPV) then inside the containment are difficult to evaluate. This leads to uncertainties in safety assessments particularly when m

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