Academic literature on the topic 'Decommissione'

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Journal articles on the topic "Decommissione"

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Barrymore, Stuart. "Decommissioning of Australia's oil and gas facilities in the 21st century." APPEA Journal 57, no. 2 (2017): 397. http://dx.doi.org/10.1071/aj16004.

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Through 2016, there has been increasing interest in the rules and regulations that apply to decommission facilities in Australia’s offshore waters. APPEA is developing guidelines as is the State of Western Australia. The Department of Industry Innovation and Research is preparing a discussion paper on Australia’s decommissioning laws, regulation and practice. It is expected to issue by the end of 2016. These developments are long overdue. Australia’s laws regarding these activities have barely changed since the offshore legislation was enacted in 1967. How major facilities are decommissioned in Australia will be a matter of interest to numerous stakeholders. It seems likely that decisions taken in the next two years will result in a modernisation of Australia’s law and practice and will determine how the major offshore facilities will be decommissioned over the next 30 years. The paper canvasses the reform process, considers the more modern regimes overseas and whether they have achieved their objectives, looks at regional (Asia–Pacific) practice and informs delegates as to the path forward on any legislative reform. The position of the States and the Commonwealth are contrasted.
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Samuels, Diane. "Catherine Yass: Decommissioned." Jewish Quarterly 60, no. 3-4 (October 2, 2013): 96–105. http://dx.doi.org/10.1080/0449010x.2013.855453.

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Swinbanks, David. "Japanese experimental nuclear reactor decommissioned." Nature 325, no. 6100 (January 1987): 100. http://dx.doi.org/10.1038/325100b0.

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Showstack, Randy. "Landsat 5 to be decommissioned." Eos, Transactions American Geophysical Union 94, no. 2 (January 8, 2013): 19. http://dx.doi.org/10.1002/2013eo020003.

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Kuznetsova, Elena, Valentina Parshina, Anastasiya Markina, and Nikita Amosov. "Comprehensive Disposal of Decommissioned Vehicles." Transportation Research Procedia 54 (2021): 362–69. http://dx.doi.org/10.1016/j.trpro.2021.02.083.

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Zhu, Yanbin, Qing Ding, Yuming Zhao, Jinwen Ai, Yan Li, and Yuan-Cheng Cao. "Study on the process of harmless treatment of residual electrolyte in battery disassembly." Waste Management & Research: The Journal for a Sustainable Circular Economy 38, no. 11 (April 20, 2020): 1295–300. http://dx.doi.org/10.1177/0734242x20914752.

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Residual electrolyte is the main pollution source in the lithium ion battery disassembly process. A practical detoxified approach is studied using the lithium hexafluorophosphate in the decommissioned power battery with dimethyl carbonate as a solvent. The pH measurement, Fourier transform infrared spectroscopy, micromorphology and phase structure characterization techniques showed that the process in this study is capable of removing lithium hexafluorophosphate from decommissioned power batteries, while controlling the proper ratio of NaOH can also completely precipitate F− into CaF2 crystal and allows recycling of the organic solvents. This process scheme of residual electrolyte treatment effectively reduces environmental pollution during the decommissioned power batteries recycling process, and has the benefit of resource reuse for valuable elements.
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Clery, Daniel. "Arecibo radio telescope to be decommissioned." Science 370, no. 6520 (November 26, 2020): 1018–19. http://dx.doi.org/10.1126/science.370.6520.1018.

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Mansour, A. E., P. T. Pedersen, and J. K. Paik. "Wave energy extraction using decommissioned ships." Ships and Offshore Structures 8, no. 5 (September 26, 2012): 504–16. http://dx.doi.org/10.1080/17445302.2012.723874.

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POLIDANO, CHARLES. "SHOULD ADMINISTRATIVE REFORM COMMISSIONS BE DECOMMISSIONED?" Public Administration 73, no. 3 (September 1995): 455–71. http://dx.doi.org/10.1111/j.1467-9299.1995.tb00838.x.

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Sens, Andrew D. "A Commission to Decommission Paramilitary Arms." World Policy Journal 23, no. 3 (September 2006): 75–85. http://dx.doi.org/10.1162/wopj.2006.23.3.75.

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Dissertations / Theses on the topic "Decommissione"

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Viehrig, Hans-Werner, Eberhard Altstadt, Mario Houska, Gudrun Mueller, Andreas Ulbricht, Joerg Konheiser, and Matti Valo. "Investigation of decommissioned reactor pressure vessels of the nuclear power plant Greifswald." Helmholtz-Zentrum Dresden - Rossendorf, 2018. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-235681.

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The investigation of reactor pressure vessel (RPV) material from the decommissioned Greifswald nuclear power plant representing the first generation of Russian-type WWER-440/V-230 reactors offers the opportunity to evaluate the real toughness response. The Greifswald RPVs of 4 units represent different material conditions as follows: • Irradiated (Unit 4), • irradiated and recovery annealed (Units 2 and 3), and • irradiated, recovery annealed and re-irradiated (Unit1). The recovery annealing of the RPV was performed at a temperature of 475° for about 152 hours and included a region covering ±0.70 m above and below the core beltline welding seam. Material samples of a diameter of 119 mm called trepans were extracted from the RPV walls. The research program is focused on the characterisation of the RPV steels (base and weld metal) across the thickness of the RPV wall. This report presents test results measured on the trepans from the beltline welding seam No. SN0.1.4. and forged base metal ring No. 0.3.1. of the Units 1 2 and 4 RPVs. The key part of the testing is focussed on the determination of the reference temperature T0 of the Master Curve (MC) approach following the ASTM standard E1921 to determine the facture toughness, and how it degrades under neutron irradiation and is recovered by thermal annealing. Other than that the mentioned test results include Charpy-V and tensile test results. Following results have been determined: • The mitigation of the neutron embrittlement of the weld and base metal by recovery annealing could be confirmed. • KJc values of the weld metals generally followed the course of the MC though with a large scatter. • There was a large variation in the T0 values evaluated across the thickness of the multilayered welding seams. • The T0 measured on T-S oriented SE(B) specimens from different thickness locations of the welding seams strongly depended on the intrinsic structure along the crack front. • The reference temperature RT0 determined according to the “Unified Procedure for Lifetime Assessment of Components and Piping in WWER NPPs - VERLIFE” and the fracture toughness lower bound curve based thereon are applicable on the investigated weld metals. • A strong scatter of the fracture toughness KJc values of the recovery annealed and re-irradiated and the irradiated base metal of Unit 1 and 4, respectively is observed with clearly more than 2% of the values below the MC for 2% fracture probability. The application of the multimodal MC-based approach was more suitable and described the temperature dependence of the KJc values in a satisfactory manner. • It was demonstrated that T0 evaluated according to the SINTAP MC extension represented the brittle fraction of the data sets and is therefore suitable for the nonhomogeneous base metal. • The efficiency of the large-scale thermal annealing of the Greifswald WWER 440/V230 Unit 1 and 2 RPVs could be confirmed.
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Stewart, Kevin Michael. "Evaluating end-of-life strategies for decommissioned semiconductor facilities." Thesis, Massachusetts Institute of Technology, 1997. http://hdl.handle.net/1721.1/44602.

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Thesis (M.B.A.)--Massachusetts Institute of Technology, Sloan School of Management; and, (S.M.)--Massachusetts Institute of Technology, Dept. of Civil and Environmental Engineering; in conjunction with the Leaders for Manufacturing Program at MIT, 1997.
Includes bibliographical references (p. 117-118).
This thesis studies the life-cycle of semiconductor facilities and the potential roles that they may play once they reach the end of their life. Specifically, the author's findings are based on studies associated with the decommissioning of a semiconductor manufacturing facility ("fab") at the Intel Corporation's Aloha Campus in Portland, Oregon. With increasing demarids for its products, Intel is constructing newer and more modern facilities to support large-scale manufacturing efforts. As newer product lines and facilities come on line, older product lines are being eliminated and older semiconductor facilities that produced them are consequently being shut down largely without regard for what their use will be afterwards. As such, this study starts by first looking at the concept of facility life-cycle with respect to semiconductor manufacturing facilities. After discussing potential pre-shutdown planning requirements, the author presents an empirical framework for evaluating possible roles that these fabrication facilities could play after they are taken out of service. In brief, the framework consists of five general steps - (1) establish reference state; (2) develop list of alternatives; (3) establish decision factors; (4) generate measures for comparison; and (5) compare and contrast to draw conclusions -and is based upon a thorough consideration of all relevant technical, strategic, and financial issues. The paper then applies the framework to a current semiconductor manufacturing facility that was the focus of this research. The example developed for Intel's Fab 4 demonstrates that a combination of a short-term role (utilizing the building as a manufacturing support platform) and a long-term strategy (combining the resources of Fab 4 and Fab 5) appears to be the "most feasible" set of alternatives. In addition, the methodology is then applied to other examples of past and potential future wafer fabrication facility decommissioning projects. Conclusions from this research indicate that a process-oriented (rather than outcome-oriented) framework best captures the iterative and dynamic nature of the problem. As such, the major contribution of this methodology is that it presents a framework for how to think about the problem rather than how to immediately solve it. As such, the author believes that the research results presented herein are not intended to be a panacea for what remains to be a difficult problem. However, since companies will no longer be able to walk away from existing facilities, the author concludes that incremental investment and planning for adaptive re-use during the facility's lifetime would appear to offer numerous advantages over waiting until after it is shut down.
by Kevin Michael Stewart.
S.M.
M.B.A.
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Ross, Justin Henry. "Evaluating ultimate bridge capacity through destructive testing of decommissioned bridges." Access to citation, abstract and download form provided by ProQuest Information and Learning Company; downloadable PDF file, 154 p, 2007. http://proquest.umi.com/pqdweb?did=1338919151&sid=8&Fmt=2&clientId=8331&RQT=309&VName=PQD.

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Thesis (M.C.E.)--University of Delaware, 2007.
Principal faculty advisors: Michael J. Chajes and Jennifer Righman McConnell, Dept. of Civil & Environmental Engineering. Includes bibliographical references.
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Farrow, Elizabeth Chapin. "A new life adaptive reuse and redevelopment of decommissioned commercial nuclear power plants /." [Gainesville, Fla.] : University of Florida, 2008. http://purl.fcla.edu/fcla/etd/UFE0023705.

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Sumsion, Eric Scott. "Condition Assessment of Decommissioned Bridge Decks Treated with Waterproofing Membranes and Asphalt Overlays." BYU ScholarsArchive, 2013. https://scholarsarchive.byu.edu/etd/4009.

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The objective of this research was to assess the condition of four decommissioned bridge decks treated with waterproofing membranes and asphalt overlays following the completion of their service lives. Large samples were cut from each of the bridge decks immediately prior to demolition and taken to the Brigham Young University Highway Materials Laboratory, where extensive sampling and testing was performed. Methods used to evaluate the condition of the bridge deck samples included visual inspection, hammer sounding, Schmidt rebound hammer testing, resistivity testing, half-cell potential testing, linear polarization testing, cover depth measurement, and chloride concentration measurement. The samples were removed from four concrete bridge decks along the Interstate 15 corridor in Provo, Utah. One bridge deck was constructed in 1937, two were constructed in 1964, and one was constructed in 1984. Each of the bridge decks was constructed using conventional cast-in-place methods. With the exception of the 1984 bridge deck, which had epoxy-coated rebar, all of the bridge decks were reinforced with black bar. A waterproofing membrane was installed on each of the bridge decks in 1984, meaning each waterproofing membrane had been in service for 26 or 27 years at the time of sampling. With the exception of one of the bridges, which was in good condition after 26 years of service, each of the bridge decks sampled had successfully served for at least 46 years. Aside from asphalt maintenance, no rehabilitation was needed on any of the bridge decks following installation of the waterproofing membranes. Without the application of the waterproofing membranes, the chloride concentrations in the bridge decks likely would have been much higher. Additional exposure to chloride ions from deicing salts would have quickly increased the chloride concentration in the concrete above critical levels, which would have led to significant corrosion and bridge deck deterioration, prematurely. While the application of membranes as a bridge deck maintenance procedure has mostly been replaced by the use of epoxy-based polymer overlays, many bridge decks protected with membrane systems are still in service today. The research findings suggest that application of waterproofing membranes and asphalt overlays in a timely manner, before the accumulation of excessive amounts of chlorides within a deck, can be an effective approach for concrete bridge deck preservation.
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Huisamen, Altus. "Quantification methods and management of hydrogeochemistry in decommissioned collieries of the Mpumalanga Coalfields." Thesis, University of Pretoria, 2017. http://hdl.handle.net/2263/63215.

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Mine water chemistry and its evolution has been the focus of various studies. However, these studies were primarily based on data from underground mines, pit lakes and mining waste dumps. Backfilled opencast mines have received limited attention in this regard and were postulated to undergo an initial flush, in a similar fashion to underground mines. Previous work in the prediction of mine water quality focussed on the fitting of an idealised decay rate curve to existing mine water chemistry data, analytical calculations, simplified geochemical modelling approaches and numerical transport models. This study has taken components from these approaches to predict the evolution of mine water quality from backfilled opencast mines, during the initial flush, but with an additional component, defining it as a new approach. This component is calibration of geochemical modelling data and numerical flow and transport modelling data, with existing groundwater monitoring data over a short term, relative to the duration of the initial flush. Laboratory analyses were further used to augment the calibration process in various steps. Results obtained show that the initial flush in backfilled opencast mines is likely to last 20 to 100 years, depending on site specific conditions. To further understand this duration, speciation modelling and statistical analysis was undertaken to determine controlling mineral phases in solution at backfilled opencast coal mines. Pyrite, gypsum, calcite, kaolinite and possible smectite were identified as the major controlling mineral phases in mine water chemistry of backfilled opencast coal mines at the study sites used for this thesis. Based on the understanding of the controlling mineral phases in solution and the calibrated mine water quality predictions made, the study also proposed the maximisation of water addition to backfilled opencast coal mines as a means to accelerate the initial flush, potentially turning contaminated mine water into a resource.
Thesis (PhD)--University of Pretoria, 2017.
Geology
PhD
Unrestricted
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Silingardi, Alberto. "Design of a Subsea Observatory to monitor the environmental impacts in a decommissioned area." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2018.

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When oil and gas fields end production, offshore installations need to be dismantled and disposed of. The set of processes used to do this could be summed up in the term Decommissioning. The Decommissioning of fixed offshore structures is one of the biggest technical and operational challenges in the O&G industry. Due to this complexity, also in term of HSE, in particular site Decommissioning could lead to potential environmental hazards which need to be monitored. The BP Miller platform is going to be completely decommissioned in the near future. Due to derogation to the OSPAR legislative framework for decommissioning in the North Sea, the Jacket footings of the platform and the contaminated drill cutting piles will remain in situ. The aim of this document is to examine the BP Miller site as a reference point to start an initial design for a subsea observatory which could be used to monitor the marine conditions around the BP Miller footings. The DELOS subsea observatory was chosen as a reference as it includes modularity in its design. This study was divided in two phases: the first phase consisted in a desktop study aimed to assess the state of art of the in-situ technology for marine environmental monitoring and the published reports about contaminated cutting piles characterization. At the end of the first phase a complete list of parameters to monitor was achieved. The second phase consisted in the conceptual design of the subsea observatory. Starting from each selected parameter, a subsea sensing technology was identified. Consequently, from the set of the chosen instruments a subsea observatory was conceived and designed following the DELOS logic which allowed adding modularity to the final project and offer the possibility to improve the design in time, following the necessary developments of the in-situ monitoring technique, which as highlighted in the first phase of the project, are steadily increasing but are far from being already effective.
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Li, Xiawen. "Power System Stability Improvement with Decommissioned Synchronous Machine Using Koopman Operator Based Model Predictive Control." Diss., Virginia Tech, 2019. http://hdl.handle.net/10919/102503.

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Traditional generators have been decommissioned or replaced by renewable energy generation due to utility long-standing goals. However, instead of flattening the entire plant, the rotating mass of generator can be utilized as a storage unit (inertia resource) to mitigate the frequency swings during transient caused by the renewables. The goal of this work is to design a control strategy utilizing the decommissioned generator interfaced with power grid via a back-to-back converter to provide inertia support. This is referred to as decoupled synchronous machine system (DSMS). On top of that, the grid-side converter is capable of providing reactive power as an auxiliary voltage controller. However, in a practical setting, for power utilities, the detailed state equations of such device as well as the complicated nonlinear power system are usually unobtainable making the controller design a challenging problem. Therefore, a model free, purely data-driven strategy for the nonlinear controller design using Koopman operator-based framework is proposed. Besides, the time delay embedding technique is adopted together with Koopman operator theory for the nonlinear system identification. Koopman operator provides a linear representation of the system and thereby the classical linear control algorithms can be applied. In this work, model predictive control is adopted to cope with the constraints of the control signals. The effectiveness and robustness of the proposed system are demonstrated in Kundur two-area system and IEEE 39-bus system.
Doctor of Philosophy
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Rasekhafshar, Samsam. "Global Fatigue Assessment of a Decommissioned Jacket Platform for a Sustainable Reuse as an Offshore Wind Turbine." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2021.

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When the offshore oil and gas supplies exhaust, offshore platforms must be decommissioned and removed. The present thesis highlights the importance of evaluating the possibility of reuse of decommissioned offshore jacket platforms for offshore wind energy. In order to shift to the new structure, the topside must be removed from the substructure and a wind turbine can be installed in its place. The feasibility of this project was investigated using a finite element analysis software called Sesam. To study fatigue life in offshore structures, an exhaustive review of the background and state of the art was done. A finite element model was created by the means of Sesam and two different fatigue analysis approaches were applied and compared. In the end, an analysis methodology is suggested for the structural fatigue analysis of offshore wind turbine structures based on international standards, addressing the industry’s need to account for the combined effect of wind and hydrodynamic loads in these type of structures.
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Miller, Malik. "The reconstruction and FEA analysis of the decommissioned WWII era destroyer USS Cassin Young in the SolidWorks environment." Thesis, Massachusetts Institute of Technology, 2013. http://hdl.handle.net/1721.1/83728.

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Thesis (S.B.)--Massachusetts Institute of Technology, Department of Mechanical Engineering, 2013.
Cataloged from PDF version of thesis.
Includes bibliographical references (page 29).
An attempt was made at reconstructing the now decommissioned World War II era destroyer USS Cassin Young using blueprints on file at the Hart Nautical Museum . After the electronic model was constructed, an attempt was made to run an FEA analysis to determine stress levels in the ship's hull. The ship was made using the various Solidworks tools available including surfacing and extrusion tools while using the available blueprints for recreation accuracy. The FEA was not completed due to problems encountered in the meshing and analysis of the complex geometry of the ship hull.
by Malik Miller.
S.B.
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Books on the topic "Decommissione"

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Kirk, Elizabeth J., ed. Decommissioned Submarines in the Russian Northwest. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9.

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Wright, George H. Towards a history of the gallows at Kennington Common (Surrey), decommissioned 1799: A monograph. [London?]: [The Author?], 1997.

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Sutherland, Euan. Modern plagues: And the decommissioned past : a set of 25 cards by Euan Sutherland. Edinburgh: New Media Scotland, 2000.

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Sarkisov, Ashot, and Alain Tournyol du Clos, eds. Scientific and Technical Issues in the Management of Spent Fuel of Decommissioned Nuclear Submarines. Dordrecht: Springer Netherlands, 2006. http://dx.doi.org/10.1007/1-4020-4173-x.

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Office, General Accounting. Nuclear regulation: Better oversight needed to ensure accumulation of funds to decommission nuclear power plants : report to congressional requesters. Washington, D.C: The Office, 1999.

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New Jersey. Legislature. General Assembly. Agriculture and Natural Resources Committee. Public hearing before Assembly Agriculture and Natural Resources Committee: Testimony on the subject of using decommissioned subway cars as artificial reefs. Trenton, N.J: Office of Legislative Services, Public Information Office, Hearing Unit, 2002.

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Steele, R. SHAG test series: Seismic research on an aged United States gate valve and on a piping system in the decommissioned Heissdampfreaktor (HDR). Washington, DC: Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

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Pressure Vessels and Piping Conference (1990 Nashville, Tenn.). Regulatory philosophy and intent of radioactive material transport: Including transport of components from decommissioned nuclear facilities : presented at the 1990 Pressure Vessels and Piping Conference, Nashville, Tennessee, June 17-21, 1990. New York, N.Y: American Society of Mechanical Engineers, 1990.

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NATO Advanced Research Workshop "Recycling, Remediation, and Restoration Strategies for Contaminated Civilian and Military Sites in the Arctic Far North" (1996 Kirkenes, Norway). Reducing wastes from decommissioned nuclear submarines in the Russian Northwest: Political, technical, and economic aspects of international cooperation : proceedings from the NATO Advanced Research Workshop "Recycling, Remediation, and Restoration Strategies for Contaminated Civilian and Military Sites in the Arctic Far North," Kirkenes, Norway, 24 to 28 June, 1996. Washington, D.C: American Association for the Advancement of Science, 1997.

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Long, J. Michael, Timothy Woodward, Allen Cardoza, Craigar Grosvenor, Lauren de Normandie, Seán Ryan, and Geoff Browne. Decommissioned. 2016.

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Book chapters on the topic "Decommissione"

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Luescher, Andreas, and Sujata Shetty. "Strategies to Address Decommissioned Automotive Plants." In Urban Shrinkage, Industrial Renewal and Automotive Plants, 81–100. Cham: Springer International Publishing, 2018. http://dx.doi.org/10.1007/978-3-030-03380-4_5.

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Gladkov, G. A., V. N. Lystsov, B. G. Pologuikh, Yu V. Siventsev, and A. P. Zotov. "Principles of Handling Decommissioned Ship Reactors." In Nuclear Submarine Decommissioning and Related Problems, 115–21. Dordrecht: Springer Netherlands, 1996. http://dx.doi.org/10.1007/978-94-009-1758-3_16.

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Gussgard, K. "Norwegian Concerns Regarding Nuclear Submarine Decommission Activities." In Nuclear Submarine Decommissioning and Related Problems, 335–37. Dordrecht: Springer Netherlands, 1996. http://dx.doi.org/10.1007/978-94-009-1758-3_41.

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Kirk, Elizabeth J. "Integration of Technical Projects with Larger Political and Economic Contexts." In Decommissioned Submarines in the Russian Northwest, 161–74. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_14.

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Lystsov, Vitaly N., and Nikolai S. Khlopkin. "Current Radioactive Contamination Issues in the Arctic North and Operation and Infrastructure of the Russian Nuclear Fleet." In Decommissioned Submarines in the Russian Northwest, 3–11. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_1.

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Landrum, Michael, Christopher A. Herbst, Eric P. Loewen, Anna Protopapas, Claire A. Chanenchuk, and Esther W. Wong. "Catalytic Extraction Process (CEP) Applications to Mixed and Radioactive Wastes and Weapons Components." In Decommissioned Submarines in the Russian Northwest, 113–25. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_10.

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Strand, Per. "Assessment of Radioactive Contamination in the Arctic." In Decommissioned Submarines in the Russian Northwest, 129–31. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_11.

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Gussgard, Knut. "Spent Nuclear Fuel Issues on the Kola Peninsula." In Decommissioned Submarines in the Russian Northwest, 133–40. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_12.

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McBean, Edward A., Frank A. Rovers, and Darrell E. O’Donnell. "Time-Risk Methodologies for Examining Remediation Technologies for Waste Contamination Sites." In Decommissioned Submarines in the Russian Northwest, 141–58. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_13.

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Ølgaard, Povl L. "Worldwide Decommissioning of Nuclear Submarines." In Decommissioned Submarines in the Russian Northwest, 13–23. Dordrecht: Springer Netherlands, 1997. http://dx.doi.org/10.1007/978-94-011-5618-9_2.

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Conference papers on the topic "Decommissione"

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Anderson, Gary, and Henning Bø. "Asset Preservation During Decommissioning and Commissioning." In ASME 2019 India Oil and Gas Pipeline Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/iogpc2019-4597.

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Operators decommission older offshore oil and gas fields for a variety of reasons: regulations and business models change, technology improves, field productivity ceases. In many cases, the existing pipeline network around these platforms is repurposed or reconfigured to suit current needs. New production wells can be tied in to the existing network, and unproductive assets can be bypassed and decommissioned. Although the platforms are most often specific in purpose, the pipelines are generalists by nature. Prolonging the life of this type of asset is almost always profitable. This paper describes how in-line isolation technology kept production loss to a minimum during offshore platform decommissioning and the tie-in of a reused pipeline into a new facility.
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Byrd, Robert C. "Realizing the Inherent Value in Decommissioned Facilities." In Offshore Technology Conference. Offshore Technology Conference, 1998. http://dx.doi.org/10.4043/8787-ms.

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"Reusing Composite Materials from Decommissioned Wind Turbine Blades." In Non-Conventional Materials and Technologies. Materials Research Forum LLC, 2018. http://dx.doi.org/10.21741/9781945291838-67.

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Peng Hou, Weihao Hu, Mohsen Soltani, Baohua Zhang, and Zhe Chen. "Optimization of decommission strategy for offshore wind farms." In 2016 IEEE Power and Energy Society General Meeting (PESGM). IEEE, 2016. http://dx.doi.org/10.1109/pesgm.2016.7741634.

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Bieber, Justin, David Ward, Samuel Bandimere, Nick Sargent, Jacqueline Foley, Norm Quail, Marc Hinton, and Malaika Ulmi. "Grouting Techniques Used to Decommission a Flowing Artesian Well." In Grouting 2017. Reston, VA: American Society of Civil Engineers, 2017. http://dx.doi.org/10.1061/9780784480786.021.

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Sexton, Richard J. "Windscale Pile Reactors: Decommissioning Progress on a Fifty Year Legacy." In The 11th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2007. http://dx.doi.org/10.1115/icem2007-7157.

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The decommissioning of the Windscale Pile 1 reactor, fifty years after the 1957 fire, is one of the most technically challenging decommissioning projects in the UK, if not the world. This paper presents a summary of the 1957 Windscale Pile 1 accident, its unique challenges and a new technical approach developed to safely and efficiently decommission the two Windscale Pile Reactors. The reactors will be decommissioned using a top down approach that employs an array of light weight, carbon fiber, high payload robotic arms to remove the damaged fuel, the graphite core, activated metals and concrete. This relatively conventional decommissioning approach has been made possible by a recently completed technical assessment of reactor core fire and criticality risk which concluded that these types of events are not credible if relatively simple controls are applied. This paper presents an overview of the design, manufacture and testing of equipment to remove the estimated 15 tons of fire damaged fuel and isotopes from the Pile 1 reactor. The paper also discusses recently conducted characterization activities which have allowed for a refined waste estimate and conditioning strategy. These data and an innovative approach have resulted in a significant reduction in the estimated project cost and schedule.
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Slavik, Ondrej, Martin Listjak, Alojz Slaninka, Jozef Moravek, Frantisek Soos, and Sylvia Dulanska. "Independent Monitoring of Radiological Impact at Decommissioned NPP A1 Site." In ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management. ASMEDC, 2009. http://dx.doi.org/10.1115/icem2009-16074.

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Monitoring of characteristics of the radiation situation in close surrounding of the decommissioned NPP A1 by an independent organization is described and discussed in the paper. The measurements are carried out in the NPP A1 site close to the VUJE operation building, not far from the places, where the decommissioning activities are concentrated. These activities relate to bringing the NPP A1 to safer conditions, e.g. cleanup of contaminated underground waste water reservoirs, solidification of the removed sludge from these reservoirs by an in situ open air solidification system, cleaning of contaminated concretes and so on. Other activities also relate to radiological impact to the environment, e.g. radioactive waste processing at Bohunice RW -Ttreatment Centre and intensive traffic of sources of ionising radiation to and from this centre located very close to the place mentioned above. Results of the measurements carried out by VUJE accredited laboratory in the frame of Decommissioning project of NPP A1 present an uninterrupted time series of measurements and enable evaluation of development for the last 17 years. The monitoring results demonstrate that the only significant radionuclide indicating radiological impact of the decommissioning is 137Cs. Its activity concentration in atmospheric aerosols at the sampling point has been time to time elevated and in average is by about one order higher in comparison with a 100 km far reference (background) site.
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Menon, Shankar, Luis Valencia, and Lucien Teunckens. "The Nuclear Decommissioner and the Regulation of Low Dose Radiation." In ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. ASMEDC, 2003. http://dx.doi.org/10.1115/icem2003-4665.

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The management of the large quantities of very low level radioactive material that arise during the decommissioning of the increasing numbers of nuclear power stations reaching the end of their commercially useful lives, has become a major subject of discussion. This has very significant economic implications for the nuclear decommissioner. Much larger quantities — 2–3 orders of magnitude larger — of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertiliser, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of TENORM, specially the activity levels and quantities arising in so many non-nuclear industries. The first reaction of international organisations seems to have been to propose different standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to thirty to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. The radiological effects of these TENORM releases have recently been dramatically highlighted by the Marina II study, which showed that over 90% of the total exposures of the European population from discharges into the North European marine waters are from radioactive discharges from non-nuclear industries. The results of an international project to validate, by actual measurement, dose calculation codes RESRAD-RECYCLE (USA) and CERISE (France) for recycling, have indicated an overestimation of doses by the codes by an order of magnitude. For the nuclear decommissioner and other producers of large volumes of slightly radioactively contaminated material, clearance levels determined on the basis of such a degree of conservatism in calculations can lead to huge volumes of material unnecessarily being condemned to burial as radioactive waste. Earlier estimates of the quantitative risk levels of exposure to ionising radiation have almost exclusively been based on doses taken by exposed populations of Hiroshima and Nagasaki (ICRP 60). The populations studied have been exposed to over 200 mSv at a dose rate of 6 Sv/s. The effects of such high dose/dose-rate exposure are being used as the basis for risk judgment at doses/dose-rates lower by a factor 1012–1015. The validity of such an extrapolation in risk judgement is an area of prime interest for discussion. In this connection, an interesting development, for both the nuclear and non-nuclear industries, is the increased scientific scrutiny that the populations of naturally high background dose level areas of the world are being subject to. Preliminary biological studies have indicated that the inhabitants of such areas, exposed to many times the permitted occupational doses for nuclear workers, have not shown any differences in cancer mortality, life expectancy, chromosome aberrations or immune function, in comparison with those living in normal background areas. The paper discusses these and other strategic issues regarding the management of redundant low radiation material from both the nuclear and non-nuclear industries, underlining the need for consistency in regulatory treatment.
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Vargemezis, G. N., P. Tsourlos, I. Fikos, G. Tsokas, and N. Kazakis. "Geoelectrical Monitoring of a Decommissioned Landfill in Thessaloniki (N. Greece)." In Near Surface Geoscience 2014 - 20th European Meeting of Environmental and Engineering Geophysics. Netherlands: EAGE Publications BV, 2014. http://dx.doi.org/10.3997/2214-4609.20142085.

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Wong, Chee, Markus R. Dann, and Ron Wong. "Life Expectancy of Decommissioned Pipelines Under External Corrosion: Probabilistic Modeling." In 2020 13th International Pipeline Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/ipc2020-9329.

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Abstract The typical service lives of operational energy pipelines are up to 50–70 years. The existing lines would subsequently be decommissioned and replaced with new lines. As one approach to dealing with a decommissioned line is by leaving the line untouched in the ground, there exists uncertainty in the structural integrity of decommissioned lines under external corrosion over time. This paper introduces reliability-based integrity assessment of decommissioned pipelines that remain in the ground. Two limit state functions are developed to quantify (i) formation of perforations under pitting corrosion, and (ii) thinning of pipe wall thickness under uniform corrosion and initiation of pipe yielding under soil and traffic loading. Corrosion occurrence and growth are modeled as stochastic processes to account for its spatio-temporal uncertainty. The reliability and safe remaining lifetime of an entire pipeline sections are determined using enhanced Monto-Carlo simulations. A sensitivity analysis is performed to identify the governing factors of the life expectancy. The proposed integrity assessment is illustrated on an example.
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Reports on the topic "Decommissione"

1

Miller, S. F., M. D. Thompson, M. G. McGinnis, and L. D. McGinnis. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground. Office of Scientific and Technical Information (OSTI), November 1992. http://dx.doi.org/10.2172/6503197.

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Cline, J. E. Characterization of decommissioned reactor internals: Direct-assay method assessment. Office of Scientific and Technical Information (OSTI), March 1993. http://dx.doi.org/10.2172/10159708.

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Miller, S. F., M. D. Thompson, M. G. McGinnis, and L. D. McGinnis. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground. Interim progress report. Office of Scientific and Technical Information (OSTI), November 1992. http://dx.doi.org/10.2172/10146723.

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Soo, P., and T. C. Roberts. Corrosion analysis of decommissioned carbon steel waste water tanks at Brookhaven National Laboratory. Office of Scientific and Technical Information (OSTI), July 1995. http://dx.doi.org/10.2172/137440.

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Love, E. F., K. A. Pauley, and B. D. Reid. Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors. Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/130639.

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M.Krug, R. Shogan. Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version). Office of Scientific and Technical Information (OSTI), September 2004. http://dx.doi.org/10.2172/837206.

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M. Krug, R. Shogan, A. Fero, and M. Snyder. Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version). Office of Scientific and Technical Information (OSTI), November 2004. http://dx.doi.org/10.2172/836105.

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Moran, B., W. Stern, J. Colley, and M. Marzo. Enhancing Efficiency of Safeguards at Facilities that are Shutdown or Closed-Down, including those being Decommissioned. Office of Scientific and Technical Information (OSTI), December 2016. http://dx.doi.org/10.2172/1389214.

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Parsons, M. B., P. W. B. Friske, A. M. Laidlow, and H. E. Jamieson. Controls on uranium, rare earth element, and radionuclide mobility at the decommissioned Bicroft Uranium Mine, Ontario. Natural Resources Canada/ESS/Scientific and Technical Publishing Services, 2014. http://dx.doi.org/10.4095/293623.

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Zimmerman, Brian, and Michele Miller. 2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site, July 2016. Office of Scientific and Technical Information (OSTI), July 2016. http://dx.doi.org/10.2172/1345387.

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