PPT-Modelling of the tritium fuel cycle
Author : celsa-spraggs | Published Date : 2018-11-14
Carlos Moreno CIEMAT 2 nd EUUS DCLL Workshop University of California Los Angeles Nov 1415 th 2014 Roadmap to DEMO Fuel Cycle schema FC requirements FC libraries
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Modelling of the tritium fuel cycle: Transcript
Carlos Moreno CIEMAT 2 nd EUUS DCLL Workshop University of California Los Angeles Nov 1415 th 2014 Roadmap to DEMO Fuel Cycle schema FC requirements FC libraries Current Model. 82 CFC-113CFC-11CFC-12SF6 (x100) Environmental tracers are natural and anthropogenic (manmade) chemical and isotopic substances that can be measured in ground water and used to understand 83 analysis - What We Learned from TFTR -. C. A. Gentile. June 24, 2014. . PPPL / ITER Workshop. 1. From 1993 to 1997 the TFTR Project processed ~ 99 grams of . tritium in support of D-T operations.. Stuart Henderson. Associate Laboratory Director for Accelerators. Community Advisory Board Meeting. August 23, 2012. Outline. What is Tritium? . How and where is it produced?. How are we managing tritium?. Blanket. Part I: Background, Choice of design, Choice of . breeder, Tritium permeation and separation. Matt Torrico. NRE 4610: Intro to Fusion. Dec. 7. th. , 2015. Introduction. The DD fuel cycle requires ion temperatures ~10x greater than. Part II: Coolant Properties, Shielding, and Tritium Breeding Ratio. Nicholas Alfred. NRE 4610-A :Intro to Fusion. Dec 7. th. , 2015. 500. Why Li17Pb83. High density . [~. 9015. . kg/(m^3. )] [1] . (and therefore a high mass flow rate can be obtained at lower velocities). Tritium. Studies in TITAN for. Lead Lithium Eutectic Blankets. P. . Calderoni. - . Idaho National Laboratory. S. . Fukada. - . Kyushu University. Y. . Hatano. - . Toyama University. S. . Konishi. Blanket. Part I: Background, Choice of design, Choice of . breeder, Tritium permeation and separation. Matt Torrico. NRE 4610: Intro to Fusion. Dec. 7. th. , 2015. Introduction. The DD fuel cycle requires ion temperatures ~10x greater than. CONTENTS. Ⅰ. Characteristics of CANDU Reactor & . Tritium. Ⅱ. Tritium Measurements. Ⅲ. Needs of the equipment development. Ⅳ. Automatic Multiple Tritium Sampler(AMTS). Ⅴ. Conclusions & Expectations . Tulipano. Phys 43, SRJC. 12 May 2009. Is nuclear power the answer?. . Transportation contributes to over 50% of CO. 2. emissions, but nuclear power cannot directly reduce this.. There are no direct greenhouse gas emissions from nuclear power.. Carlos Moreno. CIEMAT. 2. nd. EU-US DCLL Workshop University of California, Los Angeles, Nov. 14-15. th. , 2014. Roadmap . to DEMO. Fuel . Cycle schema. FC . requirements. FC . libraries. Current . Model. in Large Helical Device. The . tritium tracer study in the first deuterium plasma experiment in LHD was revealed . that: . Tritium exhaust rate was 35.5 % at the end of the plasma . experiment. Thus, . MEDIA CONTACTScott ShawPhone: 8039042Email: scott.shaw@srnl.doe.gov FOR USE: ImmediateSRNLReceives 2 INFUSE Awards Will Partner Network for Fusion Energy, or the INFUSE program, is focused on accelera Problem Summary. The trouble with tritium is there . is. no trouble with tritium.. James Conca. Fukushima Tritiated Water Tanks. Fukushima Tritiated Water Controversy. The Real Problem. : There are many people who are very angry with the decision to dump . | PAGE . 1. CEA – SPRC . | Guillaume . Krivtchik. 3rd . Technical. Workshop on Fuel Cycle Simulation. 3rd Technical Workshop on Fuel Cycle Simulation | 9-11 JULY 2018. Inspired by the uncertainty breakout session talks from TW FCS 2 – Columbia.
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