Relevant bibliographies by topics / International Thermonuclear Experimental Reactor

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'International Thermonuclear Experimental Reactor'

Author: Grafiati
Published: 4 June 2021
Last updated: 30 May 2022

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Journal articles on the topic "International Thermonuclear Experimental Reactor"

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MATSUDA, SHINZABURO. "International Thermonuclear Experimental Reactor-ITER." Journal of the Institute of Electrical Engineers of Japan 117, no. 4 (1997): 235–38. http://dx.doi.org/10.1541/ieejjournal.117.235.

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Tomabechi, Ken. "International thermonuclear experimental reactor, ITER." Fusion Engineering and Design 8 (January 1989): 43–49. http://dx.doi.org/10.1016/s0920-3796(89)80085-7.

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Conn, Robert W., Valery A. Chuyanov, Nobuyuki Inoue, and Donald R. Sweetman. "The International Thermonuclear Experimental Reactor." Scientific American 266, no. 4 (April 1992): 102–10. http://dx.doi.org/10.1038/scientificamerican0492-102.

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Aymar, R. "The International Thermonuclear Experimental Reactor." Fusion Technology 30, no. 3P2A (December 1996): 397–403. http://dx.doi.org/10.13182/fst96-a11962974.

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Tomabechi, K. "International Thermonuclear Experimental Reactor (ITER)." Revue Générale Nucléaire, no. 1 (January 1991): 95–98. http://dx.doi.org/10.1051/rgn/19911095.

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Sessler, Andrew M., Thomas H. Stix, and Marshall N. Rosenbluth. "Build the International Thermonuclear Experimental Reactor?" Physics Today 49, no. 6 (June 1996): 21–25. http://dx.doi.org/10.1063/1.881499.

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Grammatico-Vidal, Laetitia. "The International Thermonuclear Experimental Reactor (ITER) International Organisation." Nuclear Law Bulletin 2009, no. 2 (December 24, 2009): 103–13. http://dx.doi.org/10.1787/nuclear_law-v2009-art17-en.

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Clarke, John F. "Status of the International Thermonuclear Experimental Reactor." Journal of Fusion Energy 10, no. 2 (June 1991): 189–90. http://dx.doi.org/10.1007/bf01050625.

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Sugihara, Masayoshi, and Toshihide Tsunematsu. "Physics design of ITER(international thermonuclear experimental reactor)." Kakuyūgō kenkyū 65, no. 2 (1991): 142–66. http://dx.doi.org/10.1585/jspf1958.65.142.

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Henning, C. D., and J. R. Miller. "Magnet systems for the International Thermonuclear Experimental Reactor." IEEE Transactions on Magnetics 25, no. 2 (March 1989): 1469–72. http://dx.doi.org/10.1109/20.92573.

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Dissertations / Theses on the topic "International Thermonuclear Experimental Reactor"

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Bondarenko, О. О. "International thermonuclear experimental reactor." Thesis, Сумський державний університет, 2012. http://essuir.sumdu.edu.ua/handle/123456789/28681.

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ITER (originally an acronym of International Thermonuclear Experimental Reactor) is an international nuclear fusion research and engineering project, which is currently building the world's largest and most advanced experimental tokamak nuclear fusion reactor at Cadarache in the south of France. When you are citing the document, use the following link http://essuir.sumdu.edu.ua/handle/123456789/28681
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Tanna, Vipulkumar L. "Design and analysis of the superconducting current feeder system for the international thermonuclear experimental reactor (ITER)." Karlsruhe : Forschungszentrum Karlsruhe, 2006. http://d-nb.info/983081425/34.

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Commaux, Nicolas. "Contrôle du profil de densité dans le plasma de Tore Supra : comparaison de différentes méthodes d'alimentation en particules." Paris 11, 2007. http://www.theses.fr/2007PA112207.

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Le comportement d’un plasma de réacteur en fonction de la méthode utilisée pour l’alimenter en particules est difficile à prévoir. Le travail présente ici a été réalisé sur Tore Supra. 2 sujets ont été étudiés : la comparaison du comportement d’un plasma a forte fraction de la densité de Greenwald selon la manière dont il est alimenté et l’étude de l’homogénéisation de la matière déposée par un glaçon (mode d’alimentation prévu pour ITER). Les expériences à forte fraction de Greenwald effectuées sur Tore Supra ont montré que le comportement du plasma dépend de la méthode d'alimentation. Le confinement de l'énergie avec les glaçons est en accord avec les prévisions établies. Ce comportement est moins favorable pour une alimentation par injection supersonique ou classique car une perte de confinement est ici observée. Ce phénomène n'est pas lié au transport mais à la position du dépôt de matière (au bord pour le gaz et au coeur pour les glaçons). Le travail concernant l'homogénéisation de la matière déposée par une injection de glaçon a pour but d'étudier le mouvement de dérive éjectant la matière déposée vers le côté faible champ. Un nouveau phénomène a été mis en évidence : l'influence des surfaces magnétiques à facteur de sécurité (q) entier. Quand la matière dérivant vers le côté faible champ traverse une telle surface, elle subit un phénomène qui arrête la dérive. Ce travail montre aussi que le mouvement de dérive suivant une injection de glaçon côté fort champ est négligeable sur Tore Supra. Cette étude confirme que l'alimentation par injection de glaçons sera un moyen essentiel d'alimentation pour ITER et que l'injection côté faible champ pourrait être reconsidéré
The behaviour of a reactor-class plasma when fuelled using the existing techniques is difficult to foresee. The present work has been initiated on Tore Supra. Two topics have been studied: the comparison of the plasma behaviour when fuelled using the different techniques at high Greenwald density fractions and the study of the homogenisation following a pellet injection (fuelling technique for ITER burning plasmas). The experiments at high Greenwald density fractions performed on Tore Supra showed that the plasma behaviour is dependent on the fuelling method. The plasma energy confinement is following the scaling laws determined at low density when fuelled using pellet injection, which is better than for gas puffing and supersonic injection, both inducing a significant confinement loss. This behaviour is not related to transport but to the position of the matter source (at the edge for gas and close to the centre for pellets). The study concerning the homogenisation phenomena following a pellet injection aims to study the drift effect that expels the mater deposited toward the low field side. A new phenomenon was discovered: the influence of magnetic surfaces with an integer-valued safety factor (q). When the mater drifting toward low field side crosses an integer q surface, it experiences an effect that stops the drift motion. This study allows also determining that the drift following a pellet high field side injection appears negligible in Tore Supra. This work confirms that the pellet injection is an important tool for ITER plasma fuelling and that the low field side injection scheme should not be totally withdrawn for fuelling
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Tanna, Vipulkumar L. [Verfasser]. "Design and analysis of the superconducting current feeder system for the international thermonuclear experimental reactor (ITER) / Vipulkumar L. Tanna." Karlsruhe : Forschungszentrum Karlsruhe, 2006. http://d-nb.info/983081425/34.

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Kurganov, T., and A. Litovka. "ITER is a challenge of global society." Thesis, Sumy State University, 2016. http://essuir.sumdu.edu.ua/handle/123456789/45005.

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Nowadays, humanity requires more and more and more energy. What is more, present sources of energy can‘t provide modern society with it, besides, they are not rational and ecological enough, so that tends to be the only way to create new, radically new, source of energy and it is fusion reactor. Fusion reactor is a source of energy of new generation. ITER (International Thermonuclear Experimental Reactor) is a first step to create a commercially viable reactor.
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Books on the topic "International Thermonuclear Experimental Reactor"

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Canadian Fusion Fuels Technology Project., ed. International thermonuclear experimental reactor: A Canadian involvement. Mississauga, Canada: Ontario Hydro, 1989.

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United States. Dept. of Energy. Office of Energy Research, ed. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report. [Washington, D.C.]: U.S. Dept. of Energy, Office of Energy Research, 1997.

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Fusion research: Costs of ending DOE's participation in the International Thermonuclear Reactor project appear reasonable. Washington, D.C. (P.O. Box 37050, Washington, D.C. 20013): The Office, 1999.

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Knoepfel, Heinz. Tokamak Start-Up: Problems and Scenarios Related to the Transient Phases of a Thermonuclear Fusion Reactor (Ettor Majorana International Science Series) ... Science Series: Physical Sciences). Springer, 1999.

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Book chapters on the topic "International Thermonuclear Experimental Reactor"

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Reinders, L. J. "The International Thermonuclear Experimental Reactor." In Sun in a Bottle?... Pie in the Sky!, 121–45. Cham: Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-74734-3_10.

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Reinders, L. J. "The International Thermonuclear Experimental Reactor." In The Fairy Tale of Nuclear Fusion, 241–77. Cham: Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-64344-7_10.

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Gregory, E., E. Gulko, T. Pyon, and L. F. Goodrich. "Properties of Internal-Tin Nb3Sn Strand for the International Thermonuclear Experimental Reactor." In Advances in Cryogenic Engineering Materials, 1319–28. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9059-7_171.

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Aucott, Lee, Rob Bamber, Artem Lunev, Tim Darby, Philippe Maquet, Nathalie Gimbert, Sunil Pak, et al. "Solid-State Diffusion Bonding of Glass-Metal for the International Thermonuclear Experimental Reactor (ITER) Diagnostic Windows." In TMS 2020 149th Annual Meeting & Exhibition Supplemental Proceedings, 2085–94. Cham: Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-36296-6_191.

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Voitsenya, V. S., A. F. Bardamid, V. L. Berezhnyj, Yu N. Borisenko, V. I. Gritsyna, V. T. Gritsyna, V. G. Konovalov, et al. "Imitation of Fusion Reactor Environment Effects on the Inner Elements of Spectroscopical, MM and Sub-MM Diagnostics." In Diagnostics for Experimental Thermonuclear Fusion Reactors, 61–70. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4613-0369-5_6.

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Ivanov, Andrei A., Sergei N. Tugarinov, Igor N. Rastyagaev, Vladimir N. Amosov, Yuri A. Kaschuck, Anatoli V. Krasilnikov, and Sergei E. Bender. "Investigation of the Fiber Optic Radiating Resistance and Radioluminescence Under Ir-8 Reactor Condition." In Diagnostics for Experimental Thermonuclear Fusion Reactors 2, 287–90. Boston, MA: Springer US, 1998. http://dx.doi.org/10.1007/978-1-4615-5353-3_34.

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Roskoff, Nathan J., Alireza Haghighat, and Valerio Mascolino. "Experimental and Computational Validation of RAPID." In Reactor Dosimetry: 16th International Symposium, 544–54. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2018. http://dx.doi.org/10.1520/stp160820170094.

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Matěj, Zdeněk, Michal Košt´ál, Filip Mravec, Martin Pavelek, Ondřej Herman, Martin Veškrna, Václav Přenosil, František Cvachovec, and Evžen Losa. "Fast Two-Parametric Spectrometric System for Experimental MSR/FHR Reactor Dosimetry." In Reactor Dosimetry: 16th International Symposium, 63–73. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2018. http://dx.doi.org/10.1520/stp160820170129.

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Kornilov, N., T. Massey, S. Grimes, and A. Voinov. "New Experimental Proposal for235U PFNS Measurement to Answer a Fifty Year Old Question." In Reactor Dosimetry: 14th International Symposium, 721–29. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp155020120055.

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Kornilov, N., T. Massey, S. Grimes, and A. Voinov. "New Experimental Proposal for235U PFNS Measurement to Answer a Fifty Year Old Question." In Reactor Dosimetry: 14th International Symposium, 721–29. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2012. http://dx.doi.org/10.1520/stp49652t.

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Conference papers on the topic "International Thermonuclear Experimental Reactor"

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Akiba, Masato, Satoshi Suzuki, and Masanori Araki. "Thermal-cycling experiments of monoblock divertor mockups for international thermonuclear experimental reactor." In San Diego '92, edited by Ali M. Khounsary. SPIE, 1993. http://dx.doi.org/10.1117/12.140524.

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Chen, Dapeng, Guang Zhang, Xiaolong Zhang, and Zhi Zeng. "Transmission thermography for inspecting the busbar insulation layer in thermonuclear experimental reactor." In International Symposium on Optoelectronic Technology and Application 2014, edited by Mircea Guina, Haimei Gong, Zhichuan Niu, and Jin Lu. SPIE, 2014. http://dx.doi.org/10.1117/12.2071470.

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Castro, R. G., A. H. Bartlett, K. E. Elliot, and K. J. Hollis. "The Structure and Thermal Properties of Plasma Sprayed Beryllium for the International Thermonuclear Experimental Reactor (ITER)." In ITSC 1996, edited by C. C. Berndt. ASM International, 1996. http://dx.doi.org/10.31399/asm.cp.itsc1996p0735.

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Abstract Plasma spraying is under investigation as a method for in-situ repair of damaged beryllium and tungsten plasma facing surfaces for the International Thermonuclear Experimental Reactor (ITER), the next generation magnetic fusion energy device, and is also being considered as a potential fabrication method for beryllium and tungsten plasma-facing components for the first wall of ITER. Investigators at the Los Alamos National Laboratory's Beryllium Atomization and Thermal Spray Facility have concentrated on investigating the structure property relationship between the as-deposited microstructures of plasma sprayed beryllium coatings and the resulting thermal properties of the coatings. In this study, the effect of the initial substrate temperature on the resulting thermal diffusivity of the beryllium coatings and the thermal diffusivity at the coating/beryllium substrate interface (i.e. interface thermal resistance) was investigated. Results have shown that initial beryllium substrate temperatures greater than 600°C can improve the thermal diffusivity of the beryllium coatings and minimize any thermal resistance at the interface between the beryllium coating and beryllium substrate.
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Xiaochuan Liu, Yu Wu, Zhenmao Chen, Hongda Zhao, Wenlu Cai, and Patrick Vertongen. "Eddy current test research for eccentricity of international thermonuclear experimental reactor (ITER) in-vessel coils (IVCs) conductor." In 2014 IEEE Far East Forum on Nondestructive Evaluation/Testing (FENDT). IEEE, 2014. http://dx.doi.org/10.1109/fendt.2014.6928259.

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Ose, Yasuo, Kazuyuki Takase, Hiroyuki Yoshida, and Hajime Akimoto. "Numerical Visualization of Water-Vapor Flow Configurations in Fusion Reactors During Ingress of Coolant Events." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22376.

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An integrated Ingress-of-Coolant Event (ICE) test facility was constructed to demonstrate that the International Thermonuclear Experimental Reactor (ITER) safety design approach and design parameters for the ICE are adequate. Major objectives of the integrated ICE test facility are to estimate the performance of an integrated pressure suppression system and obtain the validation data for safety analysis codes for fusion reactors. The integrated ICE test facility simulates the current ITER components with a scaling factor of 1/1600. The modified Transient Reactor Analysis Code (TRAC) is used to verify the integrated ICE test results and clarify quantitatively the two-phase flow behavior in ITER during the ICE. From the results of the present study the effectiveness of the ITER pressure suppression system was verified experimentally, and then, water-vapor flow configurations in ITER at the ICE were visualized numerically by the three-dimensional computations using the modified TRAC.
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Arslan, Muhammad, Ma Yan, Muhammad Ali Shahzad, Lei Jinyun, and Shahroze Ahmed. "Simulated Temperature Profiles for Corrosion Products Deposited in ITER Experimental Loop." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66695.

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An experimental setup was designed to find out behavior of deposition thickness of corrosion products. This experimental setup is designed on the bases of ITER (International Thermonuclear Experimental Reactor) loop. The experiment was done for different values of pH to study its effect on the deposition thickness. System pressure was kept at 0.5 MPa with maximum limit of temperature at 150°C. The pH value was kept in the range of 7.00–10.50. Artificial corrosion particles (Fe3O4) were introduced manually in the loop, which was allowed to stabilize. Four test tubes were used to determine the thickness of deposition, and the temperature at these points were measured by thermocouples. It is also very important to determine the temperature distribution around such points, in order to establish its relationship with pH and deposition thickness. Results show that the change of temperature and pH (of coolant) have a strong effect on deposition thickness. The temperature distribution, found in the various components of the experimental loop, will be used to correlate its relation with the deposition thickness and the coolant pH in future studies.
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Kahl, D., A. A. Chen, S. Kubono, H. Yamaguchi, D. N. Binh, J. Chen, S. Cherubini, et al. "30S(\(\alpha \), p) Thermonuclear Reaction Rate from Experimental Level Structure of 34Ar." In Proceedings of the 14th International Symposium on Nuclei in the Cosmos (NIC2016). Journal of the Physical Society of Japan, 2017. http://dx.doi.org/10.7566/jpscp.14.020510.

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Li, Guoqing, Chao Xing, Yexi Kang, and Xiaozhen Li. "Consideration on Selection of Design Codes and Standards for China Fusion Engineering Testing Reactor." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-15476.

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After establishment of national integration design group for magnetic confinement fusion reactor in 2011, China has started its concept design activities for China Fusion Engineering Testing Reactor (hereinafter referred to as CFETR). According to the design goals of CFETR, it will be a nuclear facility contain self-sustained tritium cycle loop. As a nuclear facility, in order to assure the safety and reliability of design results of CFETR, all design should be based on existing codes and standards, or some special specifications. This paper will give introductions to existing major codes and standards in the field of magnetic confinement fusion, including the codes published by American Society of Mechanical Engineers (ASME), the standards published by French society for design and construction and in-service inspection rules for nuclear islands (AFCEN), the technical documents issued by International Thermonuclear Experimental Reactor (ITER) Organization, the standards published by nuclear industry and relating industries in China, and so on. After taking into account the requirements of the CFETR and the status of standardization of nuclear industry in China, the paper will analyze and discuss the considerations on how to select applicable design codes and standards for CFETR.
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Zhang, Baorui, Zhaoyang Xia, and Zhiwei Zhou. "Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65076.

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Abstract China Fusion Engineering Test Reactor (CFETR) is aimed to meet the technical gaps between International Thermonuclear Experimental Reactor (ITER) and future fusion DEMO reactors, tritium self-sufficiency must be guaranteed for the operation of fusion reactors. Helium Cooled Ceramic Breeder (HCCB) blanket is one of the promising candidate blanket schemes for CFETR. Tritium generated in Li4SiO4 pebble bed is carried out by purge gas, it is crucial to study the tritium behavior in the blanket from the tritium fuel cycle point of view. In this paper, the effective diffusivity of tritium in purge gas is conducted based on Discrete Element Method (DEM) and Computational Fluid Dynamics (CFD) coupled simulation considering the influence of the pebble bed structure. The flow characters analysis of purge gas is carried out by CFD simulation as well, which includes velocity field distribution, pressure field distribution and pressure drop. Based on the macro parameters conducted above, the tritium transport process in blanket including tritium permeation into coolant, tritium inventory in blanket and tritium carried out by purge gas is simulated based on a 2D model set up in COMSOL Multiphysics, the results can be the reference for the design of Tritium Extraction System (TES) and Coolant Purification System (CPS).
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Nakajima, H., K. Hamada, K. Okuno, K. Hada, and E. Tada. "New Cryogenic Steels and Design Approach for ITER Superconducting Magnet System." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22674.

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A new design code has been developed for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER). A superconducting magnet system is one of the key components of ITER and its design code includes new cryogenic materials and design approach with taking account of unique features of a performance of the superconducting magnet. The new materials are nitrogen strengthened austenitic stainless steels, which have a yield strength (Sy) of over 1000 MPa and fracture toughness (KIc) of over 200 MP√m at liquid helium temperature (4K). The feature of the design approach is use of the allowable stress defined by only 2/3 Sy measured at 4K. A concept and reliability of the new design approach using new cryogenic materials for the ITER superconducting magnet system are discussed in this paper.
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Reports on the topic "International Thermonuclear Experimental Reactor"

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Dean, S. O. (International Thermonuclear Experimental Reactor support). Office of Scientific and Technical Information (OSTI), October 1990. http://dx.doi.org/10.2172/6428949.

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Reuther, T. C. (Management session for the International Thermonuclear Experimental Reactor). Office of Scientific and Technical Information (OSTI), February 1990. http://dx.doi.org/10.2172/7161575.

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Myers, T. J., J. W. Brook, P. T. Spampinato, J. P. Mueller, T. E. Luzzi, and D. W. Sedgley. International Thermonuclear Experimental Reactor (ITER) neutral beam design. Office of Scientific and Technical Information (OSTI), October 1990. http://dx.doi.org/10.2172/6224460.

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Sowder, W. K. International Thermonuclear Experimental Reactor U.S. Home Team Quality Assurance Plan. Office of Scientific and Technical Information (OSTI), October 1998. http://dx.doi.org/10.2172/5164.

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Jardin, S. C., C. Kessel, and N. Pomphrey. Poloidal flux linkage requirements for the International Thermonuclear Experimental Reactor. Office of Scientific and Technical Information (OSTI), January 1994. http://dx.doi.org/10.2172/10116194.

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Reuther, T. C. (Fusion materials R D programs of the International Thermonuclear Experimental Reactor). Office of Scientific and Technical Information (OSTI), October 1990. http://dx.doi.org/10.2172/6398239.

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Smolik, G. R., B. J. Merrill, S. J. Piet, and D. F. Holland. Evaluation of graphite/steam interactions for ITER (International Thermonuclear Experimental Reactor). Office of Scientific and Technical Information (OSTI), September 1990. http://dx.doi.org/10.2172/6310658.

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Cohen, S., R. Mattas, and K. Werley. Plasma-materials interaction issues for the International Thermonuclear Experimental Reactor (ITER). Office of Scientific and Technical Information (OSTI), February 1992. http://dx.doi.org/10.2172/5588594.

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Davis, J. (Properties of candidate materials for the ITER (International Thermonuclear Experimental Reactor)). Office of Scientific and Technical Information (OSTI), September 1988. http://dx.doi.org/10.2172/5663073.

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Mattas, R. F. International Thermonuclear Experimental Reactor (ITER) divertor plate performance and lifetime considerations. Office of Scientific and Technical Information (OSTI), March 1990. http://dx.doi.org/10.2172/6938320.

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