Isotope Effects on Tritium Mass Transfer in Li 17 Pb 83 Liquid Blanket
|
|
- Rafe Edwards
- 5 years ago
- Views:
Transcription
1 CJWS-3 Kunming, China, Jun 0-3, 010 Isotope Effects on Tritium Mass Transfer in Li 17 Pb 83 Liquid Blanket S. Fukada, *Y. Edao, H. Okitsu and M. Okada Department Of Advanced Energy Engineering Science Interdisciplinary Graduate School of Engineering science Kyushu University
2 Contents 1 Background Our purpose & research 3 Experiment & Discussion 4 Conclusion 1
3 Background Necessary conditions of Tritium breeding blanket Self-sufficient tritium cycle High temperature heat recovery Inertial fusion reactor, KOYO-Fast Li 17 Pb 83 eutectic alloy ITER-TBM High tritium-breeding simplified blanket structure DCLL HCLL
4 Tritium recovery and leakage Inertial fusion reactor, KOYO-fast Furnace chamber LiPb flow 300 o C,.7m 3 /s leak Circulation pump 1GWt fusion reactor T generation rate : 1.5MCi/day Overall tritium leak : 10Ci/day T transfer 500 o C Tritium recovery Heat system exchanger Tritium recovery ratio of % is demanded!! leak Fueling system T recovery rate Power generator 3
5 Solubility [1 / Pa 0.5 ] Purpose & Recent research Temperature [ Design of tritium recovery system and evaluation of o C] tritium leakage F.Reiter(H) Chan and Veleckis(H) Katuta(H) C.H.Wu(D) In order to clarify the difference 10-8 Large difference /T [1/K] Estimation of property for tritium mass transfer in LiPb Wettability at interface between LiPb and wall materials Isotope effects in hydrogen isotope solubility Impurity effects Li composition change Experiment of H or D permeating through Li-Pb 4
6 Experiment of H, D permeating through Li-Pb A schematic diagram of the experimental apparatus Mass flow meter Glove-box Gas purification exhaust Experimental conditions H or Ar Li-Pb Temperature K H partial pressure D measurement purge Pure Fe H or D Electric furnance GC D partial pressure 10 5 H, D flow rate 5ccm Ar flow rate 5ccm Permeability, diffusivity and solubility of hydrogen isotopes in LiPb were determined by means of a permeation methd 5
7 Permeated H concentration in Ar purge gas [ppm] H permeation rate through LiPb+Fe system 10 5 Fe-H permeation Good agreement in the wide range Fe+Li 17 Pb 83 -H permeation Experiment LiPb Temp. = 873K LiPb+Fe system Fe 10 (transient-state permeation) (steady-state permeation) Time [hour] The overall hydrogen permeation rate is around 100 times higher than the LiPb and Fe dual layer system. The rate-determining step is in the diffusion in the LiPb layer 6
8 Permeation flux of H [mol/m s] H permeation flux in Li-Pb Dependence of H permeation flux, J LiPb-H, on upstream pressure PLiPbH J LiPb H ( ph,, ) upstream p P H downstream LiPb H KLiPb H DLiPb d Downstream-side Ar H K J H =1.6x p H 873K J H =1.4x p H 773K J H =1.x p H 673K J H =1.4x p H Upstream H pressure [Pa] recombination LiPb Diffusion of atom H Fe dissociation The hydrogen solubility obeys the Sieverts law H Upstream-side 7
9 Permeated H concentration in Ar purge gas [ppm] Wettability of Li-Pb with metal surfaces IF less wettability Possibility in some void generating between liquid and solid The apparent solubility is increased The follows equation is not valid when a certain amount of mirobubbles is present at the interface between LiPb and Fe 10 5 P K D Fe-H permeation Fe+Li 17 Pb 83 -H permeation (transient-state permeation) Experiment LiPb Temp. = 873K LiPb+Fe system Fe (steady-state permeation) Time [hour] LiPb H LiPb H Liquid Li-Pb Solid metal LiPb H Micro bubble Micro-bubble gives no effect on the values of P LiPb-H, D LiPb-H, K LiPb-H determined in the present permeation cell Our experimental permeation rate determined by the permeation method is in good agreement with the numerical one under the condition of no micro-bubble formation. 8
10 Diffusivity of H and D [m /s] Solubility of H and D [1 / Pa 0.5 ] Diffusivity & Solubility of H and D Diffusivity Temperature [ o C] Solubility Temperature [ o C] H permeation experiment D permeation experiment F.Reiter(H) T.Terai(T) Okamoto(T) H permeation experiment D permeation experiment Chan and Veleckis(H) F.Reiter(H) Katuta(H) C.H.Wu(D) /T [1/K] /T [1/K] There is no isotopic difference between H and D diffusivity in Li-Pb Solubility of D in Li-Pb is larger than H in Li-Pb 9
11 Isotope effects of solubility The isotope effects are correlated in terms of the harmonic oscillation model Hydrogen solubility is described by the difference in energy between the gaseous phase and the liquid metal phase. The Gibbs free-energy of each hydrogen gas under the standard condition, G k,0, is correlated to the following equation. (By R. Lasser) G k,0 R T g LkT ln 1 e 3.5 J k / T R g D k,0 B k,0 3 H-H LiPb-H k = H, HD, D, DT, T Gas phase Li-Pb phase 10
12 Isotope effects of solubility When H atoms dissolved in Li17Pb83 interstitials are assumed to vibrate in a three-dimensional isotropic harmonic oscillation mode, the vibration energy is described in terms of the zero-point energy, H,0, and the energy of excited state. Isotope effect calculated by harmonic oscillation model for H or D solution in Li-Pb ln K H K D sinh h D,0 k 3ln B T sinh h G G H,0 D,0 R H,0 g T k B T H,0 D,0 Isotope effect can be correlated by H (=h H,0 /k B T) The isotope effects are correlated in terms of the harmonic oscillation model 11
13 Tritium permeation rate through LiPb Tritium permeation rate through heat exchanger wall of a laser fusion reactor Furnace chamber LiPb flow Circulation pump 300 o C,.7m 3 /s leak T transfer 500 o C Tritium recovery Heat system exchanger leak Fueling system T recovery rate Power generator T concentration in LiPb, x T =10-8 (T/LiPb) R T >100Ci/day Necessary to develop high tritium recovery and high efficient permeation barrier 1
14 Conclusion Our recent activities on Li-Pb blanket material are introduced in the present paper. We continue the experiment and design activity for fusion reactor systems 1 3 The solubility obeys the Sieverts law regardless of various pressures. The wettability is estimated and micro-bubble gives no effect on the values of permeability, diffusivity and solubility determined in the present experiment. Solubility of D in Li-Pb is larger than H in Li-Pb. There is no isotopic difference between H and D diffusivity in Li-Pb. The isotope effects are correlated in terms of the harmonic oscillation model. Tritium permeation rate through heat exchanger wall of the laser fusion reactor are estimated and it is larger than 10Ci/day 13
15 CJWS-3
16 Effects of impurities and composition changes Decrease of electro-resistivity of Li-Pb with reaction of oxygen impurity 4Li (in Li-Pb)+O =Li O F. Barbier, FED (1997) Previous researches pointed out that some impurities affect solubility and diffusivity
17 Repeated measurement of Li17Pb melting point Melting point We checked melting point of Li-Pb several times, and we made sure that the melting temperature did not change after several hydrogenatingdehydrogenating operation of Li-Pb
18 Li and H activity of Li X Pb 1-X -H eutectic alloy system Pure Li Pb Pb H - Li+ Pb Li + Pb H - Li-Pb can constitute eutectic alloy system. 0.5 a HinLi a H x HinLi p H When x Li >0.5, electric charge of Li + is not shielded by Pb atoms, and Li + -H - ionic binding is major in Li X Pb 1-X eutectic alloy. Activity of Li is higher. When x Li <0.5, electric charge of Li + is shielded by Pb atoms, and Li + and H - ions may not be combined directly. Activity of Li is the lowest. 18
19 Properties of liquid blanket materials Li Li 0.17 Pb 0.83 FliBe vaporn pressure(800k).1pa 0.37Pa 0.011Pa latent heat 140kJ/mol 180kJ/mol 05kJ/mol viscosity 3.6x10-5 kgs/m.0x10-4 kgs/m 1.5x10-3 kgs/m density 0.48g/cm 3 9.5g/cm 3.0g/cm 3
20 Appendix 1 : Analytical equation One-dimensional diffusion equation The determining-step is diffusion in Li-Pb I.C. t=0, c=0 : B.C. t>0, x=0: t>0, x=l: W W up down P H P P c t, H 0 ", up P down 0 D LiPbH AD AD x LiPb c c x LiPbH x0 c x, c xl up, c down K s K s p H, p up H, down c LiPb D LiPbH K S L 9L JL L 4Dt 4Dt 4 e e e p H up p D H down LiPbHt 5L Dt
21 Appendix The diffusion equation in Li-Pb+pure-Fe system is as follows : 0 x Fe Fe x c, t Fe H, Fe LiPb D H, Fe c, t H, Fe The initial and boundary conditions are as follows: t 0, c H Fe 0, ch,, LiPb 0 H, LiPb c x D H, LiPb x0 c H, LiPb x ph, up ADH, Fe c H, Fe x 0, Wup, ch, Fe c p x x x Fe c 0 H, LiPb, i Fe, clipb K H, LiPb LiPb c H, Fe, i c Fe K H, Fe Fe K H, Fe, ph, down ADH, LiPb ch LiPb j, H Wdown, ch, LiPb c p x 0 x Fe LiPb p H, up LiPb K H, LiPb p H, down
22 Tritium recovery method from Li-Pb blanket Gas-liquid counter-current extraction tower using a packed column Furnace chamber LiPb flow Circulation pump T/He out 300 o C,.7m 3 /s leak leak T transfer 500 o C Tritium recovery Heat system exchanger Fueling system Power generator T recovery rate T/LiPb in He in Li-Pb Raschig ring T He C T Tritium p T,i LiPb out p T C T,i Liquid phase Gas phase Interface Ldc T k L a v kgav ( ct ct i) dz ( pt, R T G dp p, i T T g t p ) dz
23 Ratio of T permeation rate to the total T generation rate Tritium recovery ratio (E recovery )[%] Tritium recovery & permeation T concentration profiles in a packed-column and the rate of permeation T to the total T d=m d=1m d=0.5m E recovery < 99.9% Caluculation (1-c T, LiPb out /c T, LiPb in )x100(= E recovery ) Temperature 500 o C LiPb flow rate 3.5m 3 /s Flow velosity 1m/s Height of extraction column [m] 10-5 Tube diameter, d=0.1m Li-Pb flow rate [m 3 /s]
24 Calculation of packed column h The differential mass balance equation in the height direction of tower under steady-state Ldc T k L a v kgav ( ct ct i) dz ( pt, R T ) dz c T and p T are integrated to determine the column height H L N L L k a L v c c T, in c G p, i T T g t dct c HETP of gas side, H G, and liquid side, H L, for 1 inch raschig ring H G N G p GR T T, in dp T. out T T, i G v t pt, out T i T, k a g p p p dp T p H G 3.07 G0.3 L 0.51 G G D G 3 H L 1 L 430 L 0. L L D L 0.5
Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor
Studies on bi-directional hydrogen isotopes permeation through the first wall of a magnetic fusion power reactor IAEA-CRP Plasma-Wall Interaction with Reduced Activation Steel Surfaces in Fusion Devices
More informationEstimation of Tritium Recovery from a Molten Salt Blanket of FFHR
US/Japan Workshop on Power Plant Studies and Related Advanced Technologies with EU Participation, April 6-7, 2002 (San Diego, CA) Estimation of Tritium Recovery from a Molten Salt Blanket of FFHR Dept.
More informationTritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket
Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket I. Ricapito 1), P. Calderoni 1), A. Ibarra 2), C. Moreno 2), Y. Poitevin
More informationENEA Experience in PbLi Technologies
ENEA Experience in PbLi Technologies DCLL WORKSHOP- Tritium extraction technologies for EU DCLL M. Utili (ENEA) marco.utili@enea.it 14-15 November 2014 DCLL BB: Tritium extraction from Pb-16Li Tritium
More informationTritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor
Tritium Transport and Corrosion Modeling in the Fluoride Salt-Cooled High-Temperature Reactor John D. Stempien, PhD Content Based on Doctoral Thesis Defense Workshop on Tritium Control Salt Lake City,
More informationEffects of Water Vapor on Tritium Release Behavior from Solid Breeder Materials
Effects of Water Vapor on Tritium Release Behavior from Solid Breeder Materials T. Kinjyo a), M. Nishikawa a), S. Fukada b), M. Enoeda c), N. Yamashita a), T. Koyama a) a) Graduate School of Engineering
More informationTritium Technologies of ITER and DEMO breeding blankets
Tritium Technologies of ITER and DEMO breeding blankets A.Ciampichetti Current research topics in Nuclear Fusion Engineering Politecnico di Torino 18-01-2010 Outline Introduction Some Tritium properties
More informationConceptual Design of Advanced Blanket Using Liquid Li-Pb
Japan- US workshop on Fusion Power Plants and related advanced technologies with participation of EU February 5-7, 2007 at Kyoto, Japan Conceptual Design of Advanced Blanket Using Liquid Li-Pb Y. Yamamoto,
More informationSOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS
SOME CONSIDERATION IN THE TRITIUM CONTROL DESIGN OF THE SOLID BREEDER BLANKET CONCEPTS L.V. Boccaccini, N. Bekris, R. Meyder and the HCPB Design Team CBBI-13, Santa Barbara, 30th Nov.-2nd Dec. 2005 L.V.
More informationGas Chromatography Separation of H 2 -D 2 -Ar Using Pd/K
Gas Chromatography Separation of H 2 -D 2 -Ar Using Pd/K FTP/P1-06 X. J. Qian 1), D. L. Luo 1), C. Qin 1), G. Q. Huang 1), W. Yang 1) 1) China Academy of Engineering Physics, Mianyang, SiChuan, P.R.China
More informationMeasurement and modelling of hydrogen uptake and transport. Alan Turnbull
Measurement and modelling of hydrogen uptake and transport Alan Turnbull Hydrogen gas (+ H 2 O vapour, H 2 S) dissociation General and localised corrosion, cathodic protection, galvanic coupling; electroplating
More informationMass Transfer Operations
College of Engineering Tutorial # 1 Chemical Engineering Dept. 14/9/1428 1. Methane and helium gas mixture is contained in a tube at 101.32 k Pa pressure and 298 K. At one point the partial pressure methane
More informationSummary Tritium Day Workshop
Summary Tritium Day Workshop Presentations by M. Abdou, A. Loarte, L. Baylor, S. Willms, C. Day, P. Humrickhouse, M. Kovari 4th IAEA DEMO Programme Workshop November 18th, 2016 - Karlsruhe, Germany Overall
More informationHeat processes. Heat exchange
Heat processes Heat exchange Heat energy transported across a surface from higher temperature side to lower temperature side; it is a macroscopic measure of transported energies of molecular motions Temperature
More informationExperimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER
Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER P. Satyamurthy Bhabha Atomic Research Centre, India P. Satyamurthy,
More informationApparatus and Permeability of CO2 Dissolved in Water through LDPE and Nylon 6 Films
J. Pack. Set Technol Vol. 2 No. 2 (1993) Apparatus and Permeability of CO2 Dissolved in Water through LDPE and Nylon 6 Films Tsutomu NAKAGAWA*, Atsuko NARUSE*, Akon HIGUCHI* The apparatus by which the
More informationRole and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO
Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology
More informationKey words: EcosimPro, model, simulation, detritiation.
Design, modelling and simulation of the water detritiation system (WDS) of the ITER project with EcosimPro. Carlos Rodríguez Aguirre Email: carlos_vince@hotmail.com Tutor from the university: Mónica Coca
More informationElements of Strategy on Modelling Activities in the area of Test Blanket Systems
Elements of Strategy on Modelling Activities in the area of Test Blanket Systems I. Ricapito, TBM & MD Project Team, ITER Department, F4E, Barcelona (Spain) Barcelona, Sept 17 th 2014 Information Day FPA-611
More informationDesign of a Tritium Mitigation and Control System for Fluoride-salt-cooled Hightemperature THESIS
Design of a Tritium Mitigation and Control System for Fluoride-salt-cooled Hightemperature Reactor Systems THESIS Presented in Partial Fulfillment of the Requirements for the Degree Master of Science in
More informationConcept of Multi-function Fusion Reactor
Concept of Multi-function Fusion Reactor Presented by Songtao Wu Institute of Plasma Physics, Chinese Academy of Sciences, P.O. Box 1126, Hefei, Anhui, 230031, P.R. China 1. Motivation 2. MFFR Concept
More informationPreliminary system modeling for the EUROfusion Water Cooled Lithium Lead blanket
EUROFUSION WPBB-PR(16) 14558 F.R Urgorri et al. Preliminary system modeling for the EUROfusion Water Cooled Lithium Lead blanket Preprint of Paper to be submitted for publication in Tritium 2016-11t International
More informationTritium Fuel Cycle Safety
Tritium Fuel Cycle Safety W Kirk Hollis 1, Craig MV Taylor 1, Scott Willms 2 1 Los Alamos National Laboratory, 2 ITER IAEA Workshop on Fusion Energy June 14 th, 2018 Slide 1 Overview What is a Tritium
More informationCHAPTER 3 MODELLING AND ANALYSIS OF THE PACKED COLUMN
37 CHAPTER 3 MODELLING AND ANALYSIS OF THE PACKED COLUMN Absorption in a chemical process refers to a mass transfer between gas and liquid which transfers one or more components from the gas phase to the
More informationSystem for Continuous Chemical and Isotopic Purification of Hydrogen for the MuCap Experiment
MuCF07 System for Continuous Chemical and Isotopic Purification of Hydrogen for the MuCap Experiment A.A. Vasilyev a, I.A. Alekseev a, O.A. Fedorchenko a, V.A. Ganzha a, M. Hildebrandt b, P. Kammel c,
More informationCONTROL OF H 2 GAS EVOLUTION AT CATHODE DURING ELECTROCHEMICAL MACHINING OF IRON BY USING PALLADIUM BASED MEMBRANES
CONTROL OF H 2 GAS EVOLUTION AT CATHODE DURING ELECTROCHEMICAL MACHINING OF IRON BY USING PALLADIUM BASED MEMBRANES R.K Upadhyay 1, Arbind Kumar 2, P.K Srivastava 3 1 Department of Mechanical Engineering
More informationYuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute
Conceptual design of liquid metal cooled power core components for a fusion power reactor Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute Japan-US workshop on Fusion Power
More informationThe PPCS In-Vessel Component Concepts (focused on Breeding Blankets)
International School of Fusion reactor Technology Erice, July 26 August 1, 2004 The PPCS In-Vessel Component Concepts (focused on Breeding Blankets) Presented by L. Giancarli Commissariat à l Energie Atomique,
More informationFLIBE ASSESSMENTS ABSTRACT
FLIBE ASSESSMENTS Dai-Kai Sze, Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (630) 252-4838 USA Kathryn McCarthy, Idaho National Engineer & Environmental Laboratory, P.O. Box 1625,
More informationHCLL Test Blanket Module Test program in ITER
International Workshop on Liquid Metals Breeder Blankets 23-24 September 2010 CIEMAT, Madrid, Spain HCLL Test Blanket Module Test program in ITER Y. Poitevin, M. Zmitko, I. Ricapito, Fusion for Energy
More informationERT 216 HEAT & MASS TRANSFER SEM2, 2013/2014
ERT 16 HET & MSS TRNSFER SEM, 01/014 Tutorial: Principles of Mass Transfer (Part 1) gas of CH 4 and He is contained in a tube at 10 kpa pressure and 98 K. t one point the partial pressure of methane is
More informationPreliminary Safety Analysis of CH HCSB TBM
Preliminary Safety Analysis of CH HCSB TBM Presented by: Chen Zhi SWIP ITER TBM Workshop, China Vienna, Austria, IAEA, July 10-14, 2006 1 Introduction Calculation model Outline Review of CH HCSB TBM preliminary
More informationThermal Treatment of Stainless Steel towards the Zero Outgassing Rate
Thermal Treatment of Stainless Steel towards the Zero Outgassing Rate Vincenc Nemanic, Institute of Surface Engineering and Optoelectronics, Teslova 30, 1000 Ljubljana, Slovenia vincenc.nemanic@guest.arnes.si
More information11. Radioactive Waste Management AP1000 Design Control Document
CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated
More informationProgress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E)
Progress in Conceptual Research on Fusion Fission Hybrid Reactor for Energy (FFHR-E) Xue-Ming Shi Xian-Jue Peng Institute of Applied Physics and Computational Mathematics(IAPCM), BeiJing, China December
More informationElectrical Resistivity Changes with Neutron Irradiation and Implications for W Stabilizing Shells
Electrical Resistivity Changes with Neutron Irradiation and Implications for W Stabilizing Shells L. El-Guebaly Fusion Technology Institute University of Wisconsin-Madison With input from: C. Kessel (PPPL)
More informationChapter 11. Liquids and Intermolecular Forces
Chapter 11 Liquids and Intermolecular Forces States of Matter The three states of matter are 1) Solid Definite shape Definite volume 2) Liquid Indefinite shape Definite volume 3) Gas Indefinite shape Indefinite
More informationTritium Safety of Russian Test Blanket Module
Tritium Safety of Russian Test Blanket Module V.K. Kapyshev, V.G. Kovalenko, Y.S. Strebkov N.A. Dollezhal Research and Development Institute of Power Engineering, PO Box 788, Moscow 101000, Russia Abstract
More informationChem 112 Dr. Kevin Moore
Chem 112 Dr. Kevin Moore Gas Liquid Solid Polar Covalent Bond Partial Separation of Charge Electronegativity: H 2.1 Cl 3.0 H Cl δ + δ - Dipole Moment measure of the net polarity in a molecule Q Q magnitude
More informationAnalysis of tritium kinetics of SIBELIUS beryllium
Fusion Engineering and Design 51 52 (2000) 85 91 www.elsevier.com/locate/fusengdes Analysis of tritium kinetics of SIBELIUS beryllium S. Cho a, *, M.A. Abdou b a Korea Basic Science Institute, 52 Yeoeun-dong,
More informationAP1000 European 11. Radioactive Waste Management Design Control Document
CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms This section addresses the sources of radioactivity that are treated by the liquid and gaseous radwaste systems. Radioactive materials are generated
More informationTritium processing system for the ITER Li/V Blanket Test Module
Fusion Engineering and Design 39 40 (1998) 859 864 Tritium processing system for the ITER Li/V Blanket Test Module Dai-Kai Sze a, *, Thanh Q. Hua a, Mohamad A. Dagher b, Lester M. Waganer c, Mohamed A.
More informationMELCOR model development for ARIES Safety Analysis
MELCOR model development for ARIES Safety Analysis Paul Humrickhouse Brad Merrill INL ARIES Meeting UCSD San Diego, CA January 23 rd -24 th, 2012 Presentation Outline Status of MELCOR modeling for ARIES-ACT
More informationTritium Management in FHRs
Tritium Management in FHRs Ongoing and Planned Activities in Integrated Research Project Led by Georgia Tech Workshop on Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Experiments,
More informationExperience with Tritium Evolution During Irradiation of MSRE Flibe in the MITR
MIT NUCLEAR REACTOR LABORATORY AN MIT INTERDEPARTMENTAL CENTER Experience with Tritium Evolution During Irradiation of MSRE Flibe in the MITR David Carpenter Group Leader, Reactor Experiments 10/27/15
More informationSteady-state diffusion is diffusion in which the concentration of the diffusing atoms at
Chapter 7 What is steady state diffusion? Steady-state diffusion is diffusion in which the concentration of the diffusing atoms at any point, x, and hence the concentration gradient at x, in the solid,
More informationTritium Control Using Carbon Outside of Core Stephen T Lam
Tritium Control Using Carbon Outside of Core Stephen T Lam Charles Forsberg Ron Ballinger Tritium Overview Generation Thermal neutron transmutation of Li-6 Initially 0.005 wt. % Li-6 in Flibe consumed
More informationFLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD AND HEAT TRANSFER
V European Conference on Computational Fluid Dynamics ECCOMAS CFD 2010 J. C. F. Pereira and A. Sequeira (Eds) Lisbon, Portugal,14-17 June 2010 FLOW ANALYSIS IN THE HCLL-TBM ITER CHANNELS INCLUDING MHD
More informationToward the Realization of Fusion Energy
Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated
More informationFUSION TECHNOLOGY INSTITUTE
FUSION TECHNOLOGY INSTITUTE Z-Pinch (LiF) 2 -BeF 2 (flibe) Preliminary Vaporization Estimation Using the BUCKY 1-D Radiation Hydrodynamics Code W I S C O N S I N T.A. Heltemes, E.P. Marriott, G.A. Moses,
More informationIntroduction to the Tritium Workshop Day and
Introduction to the Tritium Workshop Day and Overview of the Tritium Fuel Cycle and Conditions for Tritium Fuel Self- Sufficiency and Other Tritium Issues Mohamed Abdou 4th IAEA DEMO Programme Workshop
More informationPolymer permeability and barrier properties - Application to flexible pipe design
Renewable energies Eco-friendly production Innovative transport Eco-efficient processes Sustainable resources Polymer permeability and barrier properties - Application to flexible pipe design MH. Klopffer,
More informationLecture 4. Ultrahigh Vacuum Science and Technology
Lecture 4 Ultrahigh Vacuum Science and Technology Why do we need UHV? 1 Atmosphere = 760 torr; 1 torr = 133 Pa; N ~ 2.5 10 19 molecules/cm 3 Hertz-Knudsen equation p ZW 1/ 2 ( 2mk T) At p = 10-6 Torr it
More informationPlasma & Fusion on Earth: merging age-old natural phenomena into your present and future
Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future Presented by Rick Lee Chief Operator, DIII-D Operations Manager, Energy/Fusion Outreach Program General Atomics
More informationNeutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden
Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden A. Klix1, A. Domula2, U. Fischer1, D. Gehre2 1 Karlsruhe
More informationPreparations for proof-of- principle D-T IEC experiments
14 th US-Japan Workshop on IEC October 15-16, 2012 University of Maryland Preparations for proof-of- principle D-T IEC experiments Yasushi YAMAMOTO 1, Masami Ohnishi 1, Hodaka, Osawa 1, Yuji Hatano 2 and
More informationExperimental Studies of Active Temperature Control in Solid Breeder Blankets
Experimental Studies of Active Temperature Control in Solid Breeder Blankets M. S. Tillack, A. R. Raffray, A. Y. Ying, M. A. Abdou, and P. Huemer Mechanical, Aerospace and Nuclear Engineering Department
More informationELECTROMAGNETIC LIQUID METAL WALL PHENOMENA
ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA BY BOB WOOLLEY 15-19 FEBRUARY 1999 APEX-6 MEETING LIQUID WALLS A sufficiently thick, flowing, liquid first wall and tritium breeding blanket which almost completely
More informationPart I.
Part I bblee@unimp . Introduction to Mass Transfer and Diffusion 2. Molecular Diffusion in Gasses 3. Molecular Diffusion in Liquids Part I 4. Molecular Diffusion in Biological Solutions and Gels 5. Molecular
More informationSeparation through Dialysis
Separation through Dialysis SOLVED WITH COMSOL MULTIPHYSICS 3.5a COPYRIGHT 2008. All right reserved. No part of this documentation may be photocopied or reproduced in any form without prior written consent
More informationIn-Vessel Tritium Inventory in Fusion DEMO Plant at JAERI
Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies with participation of EU January 11-13, 2005 at Tokyo, JAPAN In-Vessel Tritium Inventory in Fusion DEMO Plant at JAERI Hirofumi
More informationNeutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden
Neutronics experiments for validation of activation and neutron transport data for fusion application at the DT neutron generator of TU Dresden A. Klix1, A. Domula2, U. Fischer1, D. Gehre2, J. Henniger2,
More informationAiming at Fusion Power Tokamak
Aiming at Fusion Power Tokamak Design Limits of a Helium-cooled Large Area First Wall Module Clement Wong General Atomics International Workshop on MFE Roadmapping in the ITER Era Princeton University,
More informationTRITIUM RECOVERY FROM WASTE USING A PALLADIUM MEMBRANE REACTOR
TRITIUM RECOVERY FROM WASTE USING A PALLADIUM MEMBRANE REACTOR Stephen A. Birdsell and R. Scott Willms Los Alamos National Laboratory MS C348, Los Alamos, New Mexico 87545 ABSTRACT A large quantity of
More informationAPPENDIX Tidally induced groundwater circulation in an unconfined coastal aquifer modeled with a Hele-Shaw cell
APPENDIX Tidally induced groundwater circulation in an unconfined coastal aquifer modeled with a Hele-Shaw cell AaronJ.Mango* Mark W. Schmeeckle* David Jon Furbish* Department of Geological Sciences, Florida
More informationRecent R&D Activities on Tritium Technologies in Tritium Process Laboratory (TPL) of Japan Atomic Energy Agency (JAEA)
Recent R&D Activities on Tritium Technologies in Tritium Process Laboratory (TPL) of Japan Atomic Energy Agency (JAEA) Toshihiko Yamanishi, Takumi Hayashi, Yoshinori Kawamura, Hirofumi Nakamura, Iwai Yasunori,
More informationSteady-State Molecular Diffusion
Steady-State Molecular Diffusion This part is an application to the general differential equation of mass transfer. The objective is to solve the differential equation of mass transfer under steady state
More informationChE 344 Winter 2011 Final Exam. Open Book, Notes, and Web
ChE 344 Winter 2011 Final Exam Monday, April 25, 2011 Open Book, Notes, and Web Name Honor Code (Please sign in the space provided below) I have neither given nor received unauthorized aid on this examination,
More informationNumerical Simulation of Detritiation System for NIFS with Commercial Catalyst and Adsorbent
J. Plasma Fusion Res. SERIES, Vol. 10 (2013) Numerical Simulation of Detritiation System for NIFS with Commercial Catalyst and Adsorbent K. Munakata a,*, K. Hara a, T. Sugiyama b, K. Kotoh c, M. Tanaka
More informationPISCES W fuzz experiments: A summary of work up to now.
FNST/PFC/MASCO meeting, UCLA Aug. 2-6, 2010 W fuzz experiments: A summary of work up to now. M.J. Baldwin, R.P. Doerner, D. Nishijima University of California, San Diego, USA Why do we care about fuzz?
More informationAssignment 3: blood oxygen uptake. Lars Johansson IEI/mechanics Linköping university
Assignment 3: blood oxygen uptake Lars Johansson IEI/mechanics Linköping university 1 Introduction In the human lung, the airway branches to the terminal structures which are the alveoli. The alveoli are
More informationActivation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB
Activation Calculation for a Fusion-driven Sub-critical Experimental Breeder, FDEB K. M. Feng (Southwestern Institute of Physics, China) Presented at 8th IAEA Technical Meeting on Fusion Power Plant Safety
More informationMembrane processes selective hydromechanical diffusion-based porous nonporous
Membrane processes Separation of liquid or gaseous mixtures by mass transport through membrane (= permeation). Membrane is selective, i.e. it has different permeability for different components. Conditions
More informationTritium Control and Safety
Tritium Control and Safety Brad Merrill Fusion Safety Program 1 st APEX Electronic Meeting, February 6, 2003 Presentation Outline Temperature & tritium control approach TMAP model of solid wall AFS/Flibe
More informationDeuterium (Hydrogen) Flux Permeating through Palladium and Condensed Matter Nuclear Science
Deuterium (Hydrogen) Flux Permeating through Palladium and Condensed Matter Nuclear Science Qing M. Wei, Bin Liu, Yu X. Mo, Xing Z. Li, Shu X. Zheng, Dong X. Cao Department of Physics, Tsinghua University,
More informationCompact, spheromak-based pilot plants for the demonstration of net-gain fusion power
Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,
More informationIntroduction to Thermoelectric Materials and Devices
Introduction to Thermoelectric Materials and Devices 4th Semester of 2012 2012.03.29, Thursday Department of Energy Science Sungkyunkwan University Radioisotope Thermoelectric Generator (PbTe) Space probe
More informationEnergy Practice Test
Line Master C-29 Name: Energy Practice Test Section A. Multiple Choice Questions (10 mars) Directions: Place the letter of answer that is most correct on the line provided. 1. Which energy resource is
More informationRn assay and distillation purification
Rn assay and distillation purification of Lq. Xe for Kr Introduction Distillation purification of Xe for Kr Kr assay with API-MS detector Rn assay with XMASS prototype detector Summary Yasuo Takeuchi (Kamioka
More informationInfluence of High Magnetic Field on Fusion Reactor Blanket Processes
FT/P5-7 Influence of High Magnetic Field on Fusion Reactor Blanket Processes G. Kizane, J. Tiliks, A. Vitins, E. Kolodinska Laboratory of Radiation Chemistry of Solids, University of Latvia 4 blvd. Kronvalda,
More informationEffect of Temperature on Materials. June 20, Kamran M. Nemati. Phase Diagram
Effect of Temperature on Materials June 20, 2008 Kamran M. Nemati Phase Diagram Objective Phase diagrams are graphical representations of what phases are present in a material-system at various temperatures,
More informationA new approach for comprehensive modelling of molten salt properties
A new approach for comprehensive modelling of molten salt properties Anna L. Smith Delft University of Technology Radiation, Science & Technology Department Mekelweg 15 2625 JB Delft The Netherlands a.l.smith@tudelft.nl
More informationMr. Bracken. Intermolecular Forces Notes #1
Mr. Bracken AP Chemistry Name Period Intermolecular Forces Notes #1 States of Matter: A gas expands to fill its container, has neither a fixed volume nor shape, and is easily compressible. A liquid has
More informationWhat determines the phase of a substance? Temperature Pressure Interparticle Forces of Attraction
Liquids and Solids What determines the phase of a substance? Temperature Pressure Interparticle Forces of Attraction Types of Interparticle Forces Ionic Bonding Occurs between cations and anions Metallic
More informationThe role of PMI in MFE/IFE common research
The role of PMI in MFE/IFE common research Presented by Doerner for the Team and TITAN 1-1 Participants In 2006, Jupiter II recognized that PMI was a bridge issue between MFE and IFE R&D Both MFE and IFE
More informationMUTOMO SUB-COUNTY KCSE REVISION MOCK EXAMS 2015
MUTOMO SUB-COUNTY KCSE REVISION MOCK EXAMS 2015 233/1 CHEMISTRY PAPER 1 (THEORY) TIME: 2 HOURS SCHOOLS NET KENYA Osiligi House, Opposite KCB, Ground Floor Off Magadi Road, Ongata Rongai Tel: 0711 88 22
More informationLecture 8. Mole balance: calculations of microreactors, membrane reactors and unsteady state in tank reactors
Lecture 8 Mole balance: calculations of microreactors, membrane reactors and unsteady state in tank reactors Mole alance in terms of oncentration and Molar low Rates Working in terms of number of moles
More informationCryogenic Viscous Compressor Development and Modeling for the ITER Vacuum System
Cryogenic Viscous Compressor Development and Modeling for the ITER Vacuum System L. R. Baylor, C.N. Barbier, S. K. Combs, R.C. Duckworth, T.D. Edgemon, S. J. Meitner, M.P. Hechler, D.A. Rasmussen, R. Kersevan*,
More informationThermal conductivity measurement of two microencapsulated phase change slurries
Thermal conductivity measurement of two microencapsulated phase change slurries Xiaoli Ma (corresponding author), Siddig Omer, Wei Zhang and S. B. Riffat Institute of Sustainable Energy Technology, School
More informationBasic overall reaction for hydrogen powering
Fuel Cell Basics Basic overall reaction for hydrogen powering 2H 2 + O 2 2H 2 O Hydrogen produces electrons, protons, heat and water PEMFC Anode reaction: H 2 2H + + 2e Cathode reaction: (½)O 2 + 2H +
More informationNumerical Study on the Condensation Length of Binary Zeotropic Mixtures
1 Numerical Study on the Condensation Length of Binary Zeotropic Mixtures Han Deng, Maria Fernandino, Carlos A. Dorao 3rd Trondheim Gas Technology Conference 4 5 June, 2014 Trondheim, Norway 3rd Trondheim
More informationOxygen Reactivity of a Carbon Fiber Composite. T.D. Marshall, R.J. Pawelko, R.A. Anderl, G.R. Smolik, B.J. Merrill, R.L. Moore, D.A.
INEEL/CON-0-00574 PREPRINT Oxygen Reactivity of a Carbon Fiber Composite T.D. Marshall, R.J. Pawelko, R.A. Anderl, G.R. Smolik, B.J. Merrill, R.L. Moore, D.A. Petti September 00 nd Symposium on Fusion
More informationULOF Accident Analysis for 300 MWt Pb-Bi Coolled MOX Fuelled SPINNOR Reactor
ULOF Accident Analysis for 300 MWt Pb-Bi Coolled MOX Fuelled SPINNOR Reactor Ade afar Abdullah Electrical Engineering Department, Faculty of Technology and Vocational Education Indonesia University of
More informationFuel ash behavior importance of melting
Fuel ash behavior importance of melting Why is ash melting important? Bed agglomeration in fluidized bed boilers Bed behavior in BL recovery boilers Deposit formation and build up Corrosion of superheaters
More informationLiquids and Solutions Crib Sheet
Liquids and Solutions Crib Sheet Determining the melting point of a substance from its solubility Consider a saturated solution of B in a solvent, A. Since the solution is saturated, pure solid B is in
More informationChapter IX: Nuclear fusion
Chapter IX: Nuclear fusion 1 Summary 1. General remarks 2. Basic processes 3. Characteristics of fusion 4. Solar fusion 5. Controlled fusion 2 General remarks (1) Maximum of binding energy per nucleon
More informationDynamical Desorption Process of Oxygen on Platinum by Using a Gas Controllable H 2 j H þ Electrolyte j Pt Cell
Materials Transactions, Vol. 46, No. 5 (005) pp. 1058 to 1063 #005 The Japan Institute of Metals EXPRESS REGULAR ARTICLE Dynamical Desorption Process of Oxygen on Platinum by Using a Gas Controllable H
More informationFusion: The Ultimate Energy Source for the 21 st Century and Beyond
Fusion: The Ultimate Energy Source for the 21 st Century and Beyond Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA)
More informationChapter 11. Freedom of Motion. Comparisons of the States of Matter. Liquids, Solids, and Intermolecular Forces
Liquids, Solids, and Intermolecular Forces Chapter 11 Comparisons of the States of Matter The solid and liquid states have a much higher density than the gas state The solid and liquid states have similar
More informationPROBLEM 14.6 ( )( ) (b) Applying a species balance to a control volume about the hydrogen, dt 6 dt 6RAT dt 6RT dt
PROBLEM 14.6 KNOWN: Pressure and temperature of hydrogen stored in a spherical steel tank of prescribed diameter and thickness. FIND: (a) Initial rate of hydrogen mass loss from the tank, (b) Initial rate
More information