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Academic literature on the topic 'Blanket Creet'

Author: Grafiati

Published: 4 June 2021

Last updated: 7 February 2022

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Journal articles on the topic "Blanket Creet"

Zhao, Yan Yun, Shao Jun Liu, Chun Jing Li, Bo Yu Zhong, Gang Xu, Qun Ying Huang, and Yi Can Wu. "Study on the Creep and Fatigue Properties of CLAM Steel." Advances in Science and Technology 94 (October 2014): 12–16. http://dx.doi.org/10.4028/www.scientific.net/ast.94.12.

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China Low Activation Martensitic (CLAM) steel has been chosen as the structural material for China ITER Test Blanket Module (TBM). Creep-rupture and fatigue damage caused by high temperature and pulse stresses are two key issues for the final application of CLAM steel in China ITER TBM. In this paper, the research and development progress of the creep and fatigue behaviors of CLAM steel were presented. These results showed that CLAM steel possessed good high temperature mechanical properties.

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Gordan, Behrouz, and Azlan Bin Adnan. "Dynamic Analysis of Homogenize Earthen Dam Using Blanket Layer Technique." International Journal of Geotechnical Earthquake Engineering 4, no. 1 (January 2013): 68–82. http://dx.doi.org/10.4018/jgee.2013010105.

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Construction of earthen dams has developed quickly to access water and electricity. The earthquake phenomena can generate cracks at the crest, and transferred them to the structural body. It has occurred during the interaction between structure and reservoir. In this context, some reinforcement techniques have experienced according to the literature. They have included a perpendicular drain, prefabricated vertical drain, Geosynthetic in some layers within the structure, Pile, injection and cut off wall system on the dam foundation. Most of them controlled this aspect costly. The Finite-element method has applied via plane strain aspect using the ANSYS13. This paper evaluated effects of using blanket layer between a short homogenized earthen dam and weak foundation on the dynamic behavior throughout the seismic process. As a result, clay soil in the blanket layer with a modulus elasticity ratio equal to 2.50 between it, and loose sand of foundation has indicated the optimal approach. It has revealed that, this method can be changed the situation of the minimum and maximum value of shear stress when it has located in the middle of the foundation without the blanket layer at the end of vibration.

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Elavarasi, R. "A View on Creep Failure in Distribution Transformers." Indonesian Journal of Electrical Engineering and Computer Science 9, no. 1 (January 1, 2018): 49. http://dx.doi.org/10.11591/ijeecs.v9.i1.pp49-52.

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This paper insight about reasons of disappointment in distribution transformers. It has been suggested that crawl may be a noteworthy purpose behind such disappointments. The impact of anxiety, temperature, and material on unfaltering state killjoy rate on aluminum and copper wires (utilized as a part of 25 KVA distribution transformers) have been introduced. Proposed study affirms that the disappointment rate of aluminum wound DTs is higher than the disappointment rate of copper injury DTs in force insufficient ranges and poor conveyance systems. The higher disappointment rate of aluminum wound DTs has been credited to the lifted enduring state wet blanket rate of the aluminum wire than copper wire.

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Kasamuta, Yuuki, Fumio Ogawa, Takamoto Itoh, and Hiroyasu Tanigawa. "Evaluation of Multiaxial Creep-fatigue Strength for High Chromium Steel under Non-proportional Loading." MATEC Web of Conferences 300 (2019): 07002. http://dx.doi.org/10.1051/matecconf/201930007002.

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This study discusses the result of creep-fatigue tests of a high-chromium steel, F82H which was designed as blanket structural materials of nuclear fusion reactor, carried out at room temperature to 823K in air. Strain paths applied were a push-pull loading and a circle loading in which normal and shear strain have 90 degree phase difference. The holding times used were 180 s and 600 s. Moreover, an evaluation of failure life by taking into account intensities of creep and non-proportionality is discussed based on both the life evaluation proposed by Itoh, et al and method of modified universal slopes. Availability of the equation for the life evaluation was confirmed by comparison with conventional universal slope method.

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Bühler, L., and J. Reimann. "Thermal creep of granular breeder materials in fusion blankets." Journal of Nuclear Materials 307-311 (December 2002): 807–10. http://dx.doi.org/10.1016/s0022-3115(02)00982-0.

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Sandhya, R., Vani Shankar, K. Mariappan, M. D. Mathew, Tammana Jayakumar, and Ellappan Rajendra Kumar. "Low Cycle Fatigue and Creep-Fatigue Interaction Behaviour of Reduced Activation Ferritic Martensitic (RAFM) Steels with Varying W and Ta Contents." Advanced Materials Research 891-892 (March 2014): 383–88. http://dx.doi.org/10.4028/www.scientific.net/amr.891-892.383.

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Reduced activation ferritic/martensitic (RAFM) steels are candidate materials for the test blanket modules of ITER. Several degradation mechanisms such as thermal fatigue, low cycle fatigue, creep fatigue interaction, creep, irradiation hardening, swelling and phase instability associated irradiation embrittlement must be understood to estimate the component lifetime. The current work focuses on the effect of tungsten and tantalum on low cycle fatigue (LCF) and creep-fatigue interaction (CFI) behavior of four RAFM steels with varying W and Ta contents. Total strain controlled LCF experiments were performed under various strain amplitudes in the range +0.25% to +1% and temperatures (300 K to 873 K) in air at a constant strain rate of 3×10-3s-1 using a servo hydraulic fatigue testing system. CFI experiments were carried out at total strain amplitude of +0.6% and by applying strain hold of different durations (10 min and 30 min) in peak tension and peak compression. Both LCF and CFI life of the RAFM steels improved with the increase in tungsten and tantalum contents. Based on the amount of softening during continuous cycling, tungsten content was optimized at 1.4 wt. % and the tantalum content at 0.06 wt%. Stress relaxation obtained during creep-fatigue interaction studies showed close relation with the chemical composition of the RAFM steels. Other damaging parameters influencing fatigue life were dynamic strain ageing (DSA) occurring in the intermediate temperature regime and oxidation at elevated temperatures. Keywords: RAFM steel, low cycle fatigue, dynamic strain ageing, creep-fatigue interaction, oxidation

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Hofer, D., and M. Kamlah. "Drucker–Prager–Cap creep modelling of pebble beds in fusion blankets." Fusion Engineering and Design 73, no. 2-4 (October 2005): 105–17. http://dx.doi.org/10.1016/j.fusengdes.2005.02.002.

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Corogin, Paul T., and Walter S. Judd. "Floristic Inventory of Tiger Creek Preserve and Saddle Blanket Scrub Preserve, Polk County, Florida." Rhodora 111, no. 948 (October 2009): 448–502. http://dx.doi.org/10.3119/08-16.1.

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Asaoka, Yoshiyuki, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi, Yuichi Ogawa, Naoto Sekimura, Yuzo Fukai, et al. "Conceptual design of a breeding blanket with super-heated steam cycle for CREST-1." Fusion Engineering and Design 48, no. 3-4 (September 2000): 397–405. http://dx.doi.org/10.1016/s0920-3796(00)00149-6.

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Malik, S. N., and V. K. Sazawal. "Structural Analysis of an LMFBR Shield Assembly Duct Under Thermo-Mechanical and Seismic Loads." Journal of Pressure Vessel Technology 108, no. 2 (May 1, 1986): 151–57. http://dx.doi.org/10.1115/1.3264763.

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This paper describes the stress analysis performed to assess structural adequacy of the Clinch River Breeder Reactor (CRBR) core removable shield assemblies. Removable shield assemblies are located in the peripheral region of the core (between blanket assemblies and the fixed radial shield), and are subjected to severe cross-sectional thermal gradients and seismic loads requiring a relatively complex duct load pad design. For cost-effectiveness, the analysis was conducted in two stages. First, an elasto-plastic seismic stress analysis was performed using a detailed nonlinear finite element model (with gaps) of the load pad configuration. Next, in order to determine the total strain accumulation and the creep-fatigue damage the maximum seismic stresses combined with the “worst” thermal stresses from a single assembly model were used to perform a simplified inelastic analysis using two sets of material properties to bound the changing material conditions during reactor operation. This work demonstrated the necessity and applicability of the two simplified analysis techniques in elevated temperature structural design, i.e., the treatment of time-dependent degradation of material properties due to temperature and nuclear irradiation, and the use of time-independent finite element stress analysis results to perform a simplified creep-fatigue analysis.

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Dissertations / Theses on the topic "Blanket Creet"

Hansen, Gregory. "The Blankety-Blank of Bear Creek Camp: A Rhetorical Analysis of a Folk Drama." TopSCHOLAR®, 1987. https://digitalcommons.wku.edu/theses/2418.

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A rhetorical theory of folklore was used to interpret how summer camp staffers use a folk drama as a means of identification and as a type of artistic expression. The performance was analyzed for ethnographic information using Kenneth Burke's theory of dramatism and for artistic techniques using Burke's theory of the psychology of audience. The dramatistic pentad contextualized the performance, and this information was analyzed for motives through the delineation of dramatistic ratios. The skit's syntagmatic structure was outlined using Burke's description of five aspects of form. The analysis demonstrates that meaning is emergent through both the content and form of the symbolic action of the folk drama. Identification is achieved primarily through the presentation of motives. The aesthetic experience is created primarily through the use of form. The interpretation demonstrates that the skit's content and form can not be understood apart from each other and that understanding content and form is but one aspect of the performance's meaning.

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Creef, Brooke N. "Foster Child." Digital Archive @ GSU, 2011. http://digitalarchive.gsu.edu/art_design_theses/74.

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@font-face { font-family: "Calibri"; }p.MsoNormal, li.MsoNormal, div.MsoNormal { margin: 0in 0in 0.0001pt; text-indent: 0.5in; line-height: 200%; font-size: 11pt; font-family: "Times New Roman"; }div.Section1 { page: Section1; } Foster Child is my attempt to bring to light my love for dolls as creatures to be created and imagined again and again. In terms of childhood play, toys function and exist on many levels. Each becomes a friend to some and, in some cases, a confidant. Dolls become more than a plastic play-thing and through the eyes of the individual take on a life of their own based upon the user’s own personal experiences. What I deem my creation will inherently change to someone else’s and even to my mood. I aim to offer the ability to create and blur the lines of these creations. My work is self-explorative and tells of the circumstances from my childhood I hold close.

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Books on the topic "Blanket Creet"

Hodge, Annalie. Bygone days of Blanket Creek. [Sonora, Calif: A. Hodge], 1991.

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12 Mile Remembered Our Lives Before They Burned Our Homesteads: Flooded and burned dreams of a small community in British Columbia. Victoria, Canada: Trafford Publishing, 2008.

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Bagay, Blanked comics books. HEY ! You Want to Create Your Own Comic Book ?? a Star Is Born !: Comic Book Journal Notebook 102 Blanked Comic Pages 8,27 X 11,69 Cartoon Creat Your Own Story Adults Teenagers Kids. Independently Published, 2020.

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Book chapters on the topic "Blanket Creet"

Wohl, Ellen. "March: Water Superheroes." In Saving the Dammed. Oxford University Press, 2019. http://dx.doi.org/10.1093/oso/9780190943523.003.0006.

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By mid-March, daytime temperatures above freezing have left muddy puddles all over the unpaved road that runs above and beside the beaver meadow. This road extends to the national park trailhead farther upstream but is now closed for winter. I enter the beaver meadow on a lightly overcast day that is windy, as I expect March to be. Lack of recent snowfall and warm temperatures have caused the snowpack to shrink down, and I no longer break through into hidden pockets of air around the base of the bushy willows. I do break through the ice on my snowshoes, sinking in a slow motion that allows me to scramble and keep my feet dry . . . mostly. I sink in above the ankle at one point and the resulting icy ache makes me appreciate the ability of beavers to stay warm. The snow covering the higher peaks and the adjacent lateral moraines appears about the same, but numerous spots of bare ground have appeared along the creek banks. The remaining snow resembles a blanket draped over the undulating, grassy ground rather than an integral part of the landscape. I stand on the snowbank at the downstream end of one of the larger beaver ponds. The dam merges into a vegetated berm and appears to be intact, but I can hear water flowing swiftly somewhere beneath the snow. Most puzzling is that I can’t see where the water is going: the nearest downstream standing water has no apparent inflow or current. Mysterious, intricate plumbing surrounds me. The beaver meadow is on the move, flowing and changing, preparing for the season of birth and growth. Standing water is noticeably more abundant than a month ago. Interspersed among the ice and snow are big puddles and little ponds, some connected and draining, others isolated and still. The still pond waters have a shallow covering of meltwater underlain by ice with large, irregularly shaped air pockets trapped in the upper layer. These I can easily break with the tip of my ski pole. Thousands of tiny bubbles deeper in the ice look milky.

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Searle, Mike. "Frozen Rivers and Fault Lines." In Colliding Continents. Oxford University Press, 2013. http://dx.doi.org/10.1093/oso/9780199653003.003.0010.

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After seven summer field seasons working in the north-western Himalaya in India, I had heard of a winter trade route that must rank as one of the most outlandish journeys in the Himalaya. The largely Buddhist Kingdoms of Ladakh and Zanskar are high, arid, mountainous lands to the north of the Greater Himalayan Range and in the rain shadow of the summer monsoon. Whereas the southern slopes of the Himalaya range from dense sub-tropical jungles and bamboo forests to rhododendron woods and magnificent alpine pastures carpeted in spring flowers, the barren icy lands to the north are the realm of the snow leopard, the yak, and the golden eagles and lammergeier vultures that soar overhead. The Zanskar Valley lies immediately north-east of the 6–7,000-metre-high peaks of the Himalayan crest and has about thirty permanent settlements, including about ten Buddhist monasteries. I had seen the Zanskar Ranges from the summit of White Sail in Kulu and later spent four summer seasons mapping the geology along the main trekking routes. In summer, trekking routes cross the Himalaya westwards to Kashmir, southwards to Himachal Pradesh, and northwards to Leh, the ancient capital of Ladakh. Winter snows close the Zanskar Valley from the outside world for up to six months a year when temperatures plummet to minus 38oC. Central Zanskar is a large blank on the map, virtually inaccessible, with steepsided jagged limestone mountains and deep canyons. The Zanskar River carves a fantastic gorge through this mountain range and for only a few weeks in the middle of winter the river freezes. The Chaddur, the walk along the frozen Zanskar River, takes about ten to twelve days from Zanskar to the Indus Valley and, in winter time, was the only way in or out before the road to Kargil was constructed. I mentioned this winter trek to Ben Stephenson during our summer fieldwork in Kishtwar and he stopped suddenly, turned around, and said ‘Mike we just have to do this trek!’ So the idea of a winter journey into Zanskar was born, and four of us set off from Oxford in January 1995.

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"Primero Pusimos Las Sillas En Posición Y Después Las Mantas Encima. Tenemos Una Casita Linda Solamente Para Nosotros. Ahora Vamos a Jugar a Que Yo Soy El Papá Y Que Tu Eres La Mamá Y Podemos Hablar Como Lo Hacen Ellos Cuando Creen Que Nos Hemos Dormido. Ya? / First We Set Up the Chairs and Then We Put the Blankets On Top. Now We Have a Nice Little House Just for Us. Now Let’s Pretend That I’m the Daddy and You’re the Mommy and We Talk Like They Do When They Think We’re Asleep. Ok?" In In Case of Fire in a Foreign Land, 34–37. Duke University Press, 2002. http://dx.doi.org/10.1215/9780822383956-011.

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Conference papers on the topic "Blanket Creet"

Liu, Peng, and Linghui Ren. "Experimental Research on Creep Function of Offset Blanket in Offset Press." In 2014 International Conference on Mechatronics, Control and Electronic Engineering (MCE-14). Paris, France: Atlantis Press, 2014. http://dx.doi.org/10.2991/mce-14.2014.88.

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Couso, Daniel, Jose´ Fano, Felicidad Ferna´ndez, Elena Ferna´ndez, Julio A. Guirao, Jose´ L. Lastra, Victor J. Marti´nez, Javier Ordieres, and Iva´n Va´zquez. "Development of Codes and Standards for ITER In-Vessel Components." In ASME 2011 Pressure Vessels and Piping Conference. ASMEDC, 2011. http://dx.doi.org/10.1115/pvp2011-57611.

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This paper describes the changes made to existing version of the Structural Design Criteria for In-vessel Components (SDC-IC) within the ITER project, as a result of the revision and update process carried out recently. Several ITER components, referred to as In-vessel Components, are located inside the ITER Vacuum Vessel: (a) Blanket System: shields the Vessel and Magnets from heat and neutron fluxes; (b) Divertor: extracts heat, helium ash and impurities from the plasma; (c) Fuelling: gas injection system to introduce fuel into the Vacuum Vessel; (d) Ion Cyclotron Heating & Current Drive System: transfers energy to the plasma by electromagnetic radiation; (e) Electron Cyclotron Heating & Current Drive System: uses radio waves to heat to the plasma; (f) Neutral Beam Heating & Current Drive System: accelerates Deuterium particles into the plasma; (g) Lower Hybrid Heating & Current Drive System: drives electric current into the plasma; (h) Diagnostics: measurement systems to control plasma performance, and further understand plasma physics; (i) Test Blankets: demonstrate techniques for ensuring tritium production within the tokamak. ITER In-vessel Components will be subjected to special operating and environmental conditions (neutron radiation, high heat fluxes, electromagnetic forces, etc.). The effects of irradiation on them, including embrittlement, swelling and creep, are not addressed in the existing commercial codes. These conditions are different from conditions in fission reactors and create challenging issues related to the design of these components. For this reason the Structural Design Criteria for ITER In-vessel Components (SDC-IC) [1] was developed for design purposes. SDC-IC was based mainly on the RCC-MR [2] code, and included rules for assessment of effect of neutron irradiation. In 2008 some issues were identified: (1) Some parts had not been fully prepared to cover all needed areas for design; (2) Some important topics needed to be improved; (3) New editions of codes on pressure equipment had been published; (4) No manufacturing rules were included, so consistency between manufacturing rules to be used and design rules in SDC-IC needed to be demonstrated; (5) Compliance with the ESP (French Decree concerning the Pressure Equipment Directive 97/23/EC for non-nuclear pressure vessels) [3] and ESPN (French Order applicable for pressure vessels intended for nuclear facilities) [4] needed to be addressed. The work carried out for Fusion For Energy (European Union’s Joint Undertaking for ITER) is: (a) Modification of design rules, incorporating rules from recently developed codes, and development of specific design rules to cover ITER specific issues and operational conditions; (b) Demonstration of consistency between design rules in SDC-IC and european standards used for manufacturing, in particular EN 13445 [5]; identifying areas where consistency is not provided; (c) Assessment of the compliance with the Essential Safety Requirements of the French Regulations (ESP and ESPN).

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Cheruvu, N. S., V. P. Swaminathan, and C. D. Kinney. "Recovery of Microstructure and Mechanical Properties of Service Run GTD-111 DS Buckets." In ASME 1999 International Gas Turbine and Aeroengine Congress and Exhibition. American Society of Mechanical Engineers, 1999. http://dx.doi.org/10.1115/99-gt-425.

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Degradation of microstructure and mechanical properties of a service run GTD-111 DS blade was evaluated. The blade was coated with a CoCrAlY coating (GT-29) and had operated on a GE Model MS 5002 engine for 54,850 hours. To recover the microstructure of the degraded blade, the effect of solution treatment temperature on the microstructure and properties was evaluated. The blanks removed from the airfoil tip section were given a commonly used partial solution treatment 2050°F (1120°C) for GTD-111 and a high temperature solution treatment 2175°F (1190°C) prior to the partial solution and aging treatments. Microstructure and creep test results of these heat treated specimens revealed that the high temperature solution treatment was necessary to recover the microstructure and properties of in-service degraded GTD-111 DS buckets.

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Caro, M., P. DeMange, J. Marian, and A. Caro. "TRISO Particle and Beryllium Pebble Thermo-Mechanical Response in a Fusion/Fission Engine for Incineration of Weapons Grade Plutonium." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25014.

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Among the laser inertial fusion-fission energy (LIFE) engine concepts being considered at Lawrence Livermore National Laboratory (LLNL), weapons-grade plutonium (WGPu) LIFE is of particular interest because it is designed to burn excess WGPu material and achieve over 99% fraction of initial metal atoms (FIMAs). At the center of the LIFE concept lies a point source of 14MeV neutrons produced by inertial-confinement fusion (ICF) which drives a sub-critical fuel blanket located behind a neutron multiplier. Current design envisions tristructural isotropic (TRISO) particles embedded in a graphite matrix as fuel and Be as multiplier, both in pebble bed form and flowing in Flibe molten salt coolant. In previous work, neutron lifetime modeling and design of Be pebbles was discussed [10]. Constitutive equations were derived and a design criteria were developed for spherical Be pebbles on the basis of their thermo-mechanical behaviour under continued neutron exposure in the neutron multiplier for the LIFE engine. Utilizing the available material property data, Be pebbles lifetime could be estimated to be a minimum of 6 years. Here, we investigate the thermo-mechanical response of TRISO particles used for incineration of WUPu under LIFE operating conditions of high temperature and high neutron fast fluence. To this purpose, we make use of the thermo-mechanical fuel performance code HUPPCO, which is currently under development. The model accounts for spatial and time dependence of the material elastic properties, temperature, and irradiation swelling and creep mechanisms. Preliminary results show that the lifetime of WGPu TRISO particles is affected by changes in the fuel materials properties in time. At high fuel burnup, retention of fission products relies on the SiC containment boundary behavior as a minute pressure vessel. The discussion underlines the need to develop high-fidelity models of the performance of these new fuel designs, especially in the absence of a fast neutron source to test these fuels under relevant conditions.

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