Elements of Strategy on Modelling Activities in the area of Test Blanket Systems
|
|
- Dominick Douglas
- 5 years ago
- Views:
Transcription
1 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 TBS simulation tools 1
2 CONTENT Short recall on the main breeder blanket functions Intro to Test Blanket Systems and their mission Some elements of modelling strategy in the F4E TBM Project 2
3 Before starting. Presentation of the TBM-Project Team TBMs and Materials Development Project Team Leader Y. Poitevin Admin. Assistant: B. Gomez Integration Engineering COO: M. Ferrari Safety & Licensing analyses TPO: D. Panayotov TBM Sets COO: M. Zmitko* TPO: J. Vallory TPO: J. Galabert TPO: Y. Carin PPO: L. Romano + QAO: C. Annino LSO: I. Costin. Ancillary Systems, Instrument., modelling tools COO: I. Ricapito** TPO: P. Calderoni TPO: D. Ugolini * TRO for the delivery of HCPB-TBS to IO ** TRO for the delivery of HCLL-TBS to IO 3
4 Breeding Blanket: Functions Functions of the Breeding Blanket /1 Blanket Shield Vacuum vessel Radiation Plasma Neutrons First Wall T breeding zone Coolant Magnets TOKAMAK: toroidal-radial view HCLL-DEMO reactor (2007, CEA) THREE ESSENTIAL FUNCTIONS IMPLEMENTED BY THE BREEDING BLANKET A. Tritium breeding to achieve the tritium self-sufficiency B. Nuclear to thermal power conversion C. Neutron/γ-ray shielding 4
5 Breeding Blanket: Functions Functions of the Breeding Blanket /2 Function C: shielding Function A: tritium breeding Function B: power conversion Neutron flux radially has to decrease around 1 order of magnitude to protect VV and magnets In the plasma: T + D 4 He + n (17.6 MeV) Breeding blanket materials are heated-up because: a) Heat flux from plasma b) Nuclear heat generated by neutrons slowingdown and nuclear reactions with Li. The thermal power is then extracted by a suitable coolant and converted into electrical power through a conventional turbine-alternator group 5
6 Test Blanket Systems and their mission The TBM project provides test blankets to test and validate design concepts of tritium breeding blankets relevant to a power-producing reactor. HCLL-TBS HCPB-TBS ITER Project Requirements 6
7 Test Blanket Systems and their mission Fuelling Systems (FS) Tritium Extraction System (TES) Coolant Processing System (CPS) Cooling zone Breeder zone Storage & Delivery System (SDS) Isotope Separation System (ISS) Protium release Water Detritiation Systems (WDS) Tokamak Exhaust Processing (TEP) Detritiation Systems (DS) Accountancy System (AS) Pumping Systems (PS) Off-gas release Simplified block diagram with TES and CPS integrated in the main ITER fuel cycle 7
8 Test Blanket Systems and their mission The major overall testing objectives for each TBS shall be : validation of the structural integrity theoretical predictions under combined and relevant loads validation of the tritium breeding predictions validation of tritium recovery process efficiency validation of the T-inventories prediction in blanket materials validation of thermal predictions for strongly heterogeneous breeding blanket concepts with volumetric heat sources validation of blanket power removal predictions demonstration of the integral performance of the blankets systems Exploitation at maximum extent of the TBS experimental campaign in ITER requires a strong prediction capability developed in advance 8
9 SCOPE Developing Modelling Activities_1 Preliminarily foreseen modeling areas: Thermo-hydraulics, MHD, chemistry of Pb-16Li Tritium transport in solids, liquids, gases and interfaces Structural analysis of TBS components (including Pebble Beds thermo-mechanics) EM analysis of ferromagnetic structures Helium thermo-hydraulics Neutronics Depending on the stage of the project, modelling tools will be used in: - Correlative way for pre-validation against ad-hoc designed experimental tests - Predictive way to provide support to the TBS design /design of experiments in ITER - Correlative way during the ITER campaign, to extract relevant physical and engineering data - Predictive way to provide support to the design of DEMO BB 9
10 SCOPE Developing Modelling Activities_2 Final Objective is the production of an integrated model, to be exploited and validated during the different ITER operational phases Multi-physics Modelling Integration Test Program Instrumentation Development Modelling Integration will not be matter of this first phase of development nor of the FPA
11 Developing Modelling Activities_3 System Level (TBS) Hierarchy of the modelling layers will be compliant with the hierarchy of the elements in the systems to be modelled Sub-Systems Level (TBM, HCS, TES, PbLi-loop, T-Acc, etc.) Component Level (i.e. getter in TES, oxidizer in CPS, MSB in PSA configuration, etc.) Physics Modelling (i.e. transport through CB, permeation through steel pipe, etc) The System level tool consists of different Sub-system Tools Each Sub-system level tool consists of different Component Tools Each Component level tool contains one or more Physics Modelling sub-routines 11
12 Developing Modelling Activities_4 Preliminary Development Plan for Tritium Modelling Time Span Tritium Modeling Activities are currently the most advanced because of the implications for the conceptual design and preparation of the HCLL/HCPB- TBS Preliminary Safety Reports First Work Package: PHYSICS 1.1 Development of physics modelling subroutines 1.2 Implementation of physical parameter database through dedicated experiments on lab-scale level (separated effects) 1.3 Analysis of multiple effect impacting TT Second Work Package: COMPONENTS and Sub-SYSTEMS 2.1 Development of component model tools 2.2 Development of sub-system model 2.3 Experiments on TBS main components (mainly multiple effects) Third Work Package: INTEGRATION and Pre-VALIDATION 3.1 Integration of the component/sub-system tools into a unique system tool 3.2 Integrated experiments, also for multiple effects, before ITER for pre-validation 3.3 Integrated experiments during ITER H-H, H-He and D-D phases for pre-validation Fourth Work Package: Validation against DT Experiments 12
13 Developing Modelling Activities_5 First TBS-related modelling activities have been carried out on EM (OPE L1 TO12) and tritium modeling (GRT-254, GRT-542) have been carried out (successfully) in the last years at F4E n. 3 eight-hours shifts of back to back pulses, n. 3 values of Pb-16Li flow-rates Time evolution of the Maxwell, Lorentz and total forces for the HCLL TBM during MFD-II 13
14 Concluding Remarks I. Modelling strategy covering all duration of the TBM project is still preliminary and will be consolidated along the development f the Project II. Modelling integration is not in the scope of the first part of development III. Wide scope, covering (very) different areas, then requiring a large portfolio of technical skills IV. In the perimeter of Modelling there are also experimental activities for model/code validation V. Modelling Activities driven by TBS Project milestones, as they are in support of the TBS design and design of experiment 14
Tritium 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 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 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 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 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 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 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 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 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 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 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 informationPerspective on Fusion Energy
Perspective on Fusion Energy Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA) President, Council of Energy Research
More information1 FT/P5-15. Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor
1 FT/P5-15 Assessment of the Shielding Efficiency of the HCLL Blanket for a DEMOtype Fusion Reactor J. Jordanova 1), U. Fischer 2), P. Pereslavtsev 2), Y. Poitevin 3), J. F. Salavy 4), A. Li Puma 4), N.
More informationEU PPCS Models C & D Conceptual Design
Institut für Materialforschung III EU PPCS Models C & D Conceptual Design Presented by P. Norajitra, FZK 1 PPCS Design Studies Strategy definition [D. Maisonnier] 2 models with limited extrapolations Model
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 informationNeutronic Activation Analysis for ITER Fusion Reactor
Neutronic Activation Analysis for ITER Fusion Reactor Barbara Caiffi 100 Congresso Nazionale SIF 1 Outlook Nuclear Fusion International Thermonuclear Experimental Reactor (ITER) Neutronics Computational
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 informationA SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR
A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR A.N. Mauer, W.M. Stacey, J. Mandrekas and E.A. Hoffman Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332 1. INTRODUCTION
More informationNeutronics analysis of inboard shielding capability for a DEMO fusion reactor
*Manuscript Click here to view linked References Neutronics analysis of inboard shielding capability for a DEMO fusion reactor Songlin Liu a, Jiangang Li a, Shanliang Zheng b, Neil Mitchell c a Institute
More informationDesign concept of near term DEMO reactor with high temperature blanket
Design concept of near term DEMO reactor with high temperature blanket Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies March 16-18, 2009 Tokyo Univ. Mai Ichinose, Yasushi Yamamoto
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 informationAdaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source
Adaptation of Pb-Bi Cooled, Metal Fuel Subcritical Reactor for Use with a Tokamak Fusion Neutron Source E. Hoffman, W. Stacey, G. Kessler, D. Ulevich, J. Mandrekas, A. Mauer, C. Kirby, D. Stopp, J. Noble
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 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 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 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 informationFusion Reactor Research Activities at SWIP (1)
Fusion Reactor Research Activities at SWIP (1) Design Studies of DEMO Reactor 1. Introduction Considering that there is still a long way to go towards an economically competitive commercial fusion power
More informationFusion Nuclear Science - Pathway Assessment
Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,
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 informationStudy of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor
CCFE-PR(17)32 S. Zhen and T.N. Todd Study of Impacts on Tritium Breeding Ratio of a Fusion DEMO Reactor Enquiries about copyright and reproduction should in the first instance be addressed to the Culham
More informationSeminar Chengdu, China Southwestern Institute of Physics (SWIP)
Blanket/First Wall Challenges and Required R&D on the pathway to DEMO for the near term in laboratory experiments and medium term in FNSF/CFETR Mohamed Abdou Distinguished Professor of Engineering and
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 informationPlasma Wall Interactions in Tokamak
Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:
More informationAspects of Advanced Fuel FRC Fusion Reactors
Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 santarius@engr.wisc.edu;
More informationPhysics of fusion power. Lecture 14: Anomalous transport / ITER
Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities
More informationTritium Inventories and Tritium Safety Design Principles for the Fuel cycle of ITER
Tritium Inventories and Tritium Safety Design Principles for the Fuel cycle of ITER I. R. Cristescu 1), I. Cristescu 1), L. Doerr 1), M. Glugla 1), D. Murdoch 2), 1) Forschungszentrum Karlsruhe, Tritium
More informationFusion/transmutation reactor studies based on the spherical torus concept
FT/P1-7, FEC 2004 Fusion/transmutation reactor studies based on the spherical torus concept K.M. Feng, J.H. Huang, B.Q. Deng, G.S. Zhang, G. Hu, Z.X. Li, X.Y. Wang, T. Yuan, Z. Chen Southwestern Institute
More informationTransmutation of Minor Actinides in a Spherical
1 Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor Feng Kaiming Zhang Guoshu Fusion energy will be a long-term energy source. Great efforts have been devoted to fusion research
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 informationIssues for Neutron Calculations for ITER Fusion Reactor
Introduction Issues for Neutron Calculations for ITER Fusion Reactor Erik Nonbøl and Bent Lauritzen Risø DTU, National Laboratory for Sustainable Energy Roskilde, Denmark Outline 1. Fusion development
More informationFusion Development Facility (FDF) Mission and Concept
Fusion Development Facility (FDF) Mission and Concept Presented by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION University of California Los Angeles FNST Workshop
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 informationDesign optimization of first wall and breeder unit module size for the Indian HCCB blanket module
2018 Hefei Institutes of Physical Science, Chinese Academy of Sciences and IOP Publishing Printed in China and the UK Plasma Science and Technology (11pp) https://doi.org/10.1088/2058-6272/aab54a Design
More informationThe Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket of CFETR
J Fusion Energ (2015) 34:1088 1093 DOI 10.1007/s10894-015-9923-6 ORIGINAL RESEARCH The Development and Application of One Thermal Hydraulic Program Based on ANSYS for Design of Ceramic Breeder Blanket
More informationSafety considerations for Fusion Energy: From experimental facilities to Fusion Nuclear Science and beyond
Safety considerations for Fusion Energy: From experimental facilities to Fusion Nuclear Science and beyond 1st IAEA TM on the Safety, Design and Technology of Fusion Power Plants May 3, 2016 Susana Reyes,
More informationMission Elements of the FNSP and FNSF
Mission Elements of the FNSP and FNSF by R.D. Stambaugh PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Presented at FNST Workshop August 3, 2010 In Addition to What Will Be Learned
More informationFUSION NEUTRONICS EXPERIMENTS AT FNG: ACHIEVEMENTS IN THE PAST 10 YEARS AND FUTURE PERSPECTIVES
FUSION NEUTRONICS EXPERIMENTS AT FNG: ACHIEVEMENTS IN THE PAST 10 YEARS AND FUTURE PERSPECTIVES presented by Paola Batistoni ENEA Fusion Division Fast Neutron Physics International Workshop & IEA International
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 informationBasics of breeding blanket technology
Basics of breeding blanket technology Dr Fabio CISMONDI Karlsruher Institut für Technologie (KIT) Institut für Neutronenphysik und Reaktortechnik e-mail: fabio.cismondi@kit.edu www.kit.edu Development
More informationTECHNICAL NOTE related to the Market survey on Water Holding Tanks for the Water Detritiation System (WDS) Prepared by Reviewed by Approved by ---
Page 1 / 5 Ver. 1.1 TECHNICAL NOTE related to the Market survey on Water Holding Tanks for the Water Detritiation System (WDS) INDUSTRY SURVEY Document Reference: F4E_D_2ENZ79 Revision Number: 1.1 ITER
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 informationTHERMAL ANALYSIS OF A SOLID BREEDER TBM UNDER ITER OPERATIONAL CONDITIONS. A. Abou-Sena, A. Ying, M. Youssef, M. Abdou
THERMAL AALYSIS OF A SOLID BREEDER TBM UDER ITER OPERATIOAL CODITIOS A. Abou-Sena, A. Ying, M. Youssef, M. Abdou Mechanical and Aerospace Engineering Dep., UCLA, Los Angeles, CA 90095 aliabousena@engineering.ucla.edu
More informationBreeding Blanket Modules testing in ITER: An international program on the way to DEMO
Fusion Engineering and Design 81 (2006) 393 405 Breeding Blanket Modules testing in ITER: An international program on the way to DEMO L. Giancarli a,, V. Chuyanov b, M. Abdou c, M. Akiba d, B.G. Hong e,r.lässer
More informationTritium Plant in ITER and F4E Contribution. G. Piazza ITER Department, Fusion for Energy
Tritium Plant in ITER and F4E Contribution G. Piazza ITER Department, Fusion for Energy 1 Presentation Outline Introduction Fuel Cycle of a Fusion Reactor Overall description of the ITER Tritium Plant
More informationTechnological and Engineering Challenges of Fusion
Technological and Engineering Challenges of Fusion David Maisonnier and Jim Hayward EFDA CSU Garching (david.maisonnier@tech.efda.org) 2nd IAEA TM on First Generation of FPP PPCS-KN1 1 Outline The European
More informationNeutron Testing: What are the Options for MFE?
Neutron Testing: What are the Options for MFE? L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison http://fti.neep.wisc.edu/uwneutronicscenterofexcellence Contributors: M. Sawan
More information10.1 Functions, Basic Configuration and System Boundaries
10 Tritium Plant and Detritiation 10.1 Functions, Basic Configuration and System Boundaries 10.1.1 Functions The tritium plant shall be designed to perform the functions described in the DRG1, section
More informationITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia
N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia UKAEA, Culham Science Centre, Abingdon, Oxon,OX14 3DB, UK, nick.balshaw@jet.uk Many of the ITER diagnostic systems will be mounted in the
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 informationEUROFUSION WPBB-CP(16) F. Hernandez et al.
EUROFUSION WPBB-CP(16) 15535 F. Hernandez et al. A new HCPB breeding blanket for the EU DEMO fusion reactor: design evolution, rationale and preliminary nuclear, thermo-hydraulic and thermo-mechanical
More informationDEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor
FIP/3-4Rb FIP/3-4Ra DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, Y. Someya, H. Utoh, N. Asakura, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team
More informationPREPARATION OF HEXCALIBER TESTS AND PRELIMINARY THERMO-MECHANICAL ANALYSES
PREPARATION OF HEXCALIBER TESTS AND PRELIMINARY THERMO-MECHANICAL ANALYSES I. Ricapito a, G. Dell Orco b, P. A. Di Maio c, R. Giammusso c, A. Malavasi a, A. Tincani a, G. Vella c a ENEA C.R. Brasimone
More informationFusion Fuel Cycle. ing. Stefan Ionut SPIRIDON. Association Days, Institutefor Cryogenics and Isotopes Technologies Rm.
Association Days, 02.07.2010 Tritium Technologies for the Fusion Fuel Cycle ing. Stefan Ionut SPIRIDON Institutefor Cryogenics and Rm. Valcea 1. I. Spiridon, Tritium Technologies for the Fusion Fuel Cycle
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 informationUnpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000
From last time Fission of heavy elements produces energy Only works with 235 U, 239 Pu Fission initiated by neutron absorption. Fission products are two lighter nuclei, plus individual neutrons. These
More informationStudies 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 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 informationThermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement
EUROFUSION WPBB-CP(16) 15737 P Arena et al. Thermal optimization of the Helium-Cooled Lithium Lead breeding zone layout design regarding TBR enhancement Preprint of Paper to be submitted for publication
More informationI. Kodeli 1. INTRODUCTION
Science and Technology of Nuclear Installations Volume 2008, Article ID 659861, 5 pages doi:10.1155/2008/659861 Research Article Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design
More informationWhich Superconducting Magnets for DEMO and Future Fusion Reactors?
Which Superconducting Magnets for DEMO and Future Fusion Reactors? Reinhard Heller Inspired by Jean Luc Duchateau (CEA) INSTITUTE FOR TECHNICAL PHYSICS, FUSION MAGNETS KIT University of the State of Baden-Wuerttemberg
More informationfor the French fusion programme
The ITER era : the 10 year roadmap for the French fusion programme E. Tsitrone 1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F-13108 Saint-Paul-lez-Durance, France Association EURATOM-CEA TORE
More informationFusion Nuclear Science and Technology Challenges and Required R&D
Fusion Nuclear Science and Technology Challenges and Required R&D Mohamed Abdou Distinguished Professor of Engineering and Applied Science, UCLA Director, Fusion Science and Technology Center, UCLA Founding
More informationFirst Workshop on MFE Development Strategy in China January 5-6, 2012
ITER as a prototype of a Fission Fusion Hybrid. The fastest way to fusion power. V. Chuyanov First Workshop on MFE Development Strategy in China January 5-6, 2012 Content 1. Possible missions of nuclear
More informationGA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO
GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO by C.P.C. WONG and R.D. STAMBAUGH JULY 1999 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United
More informationNuclear Analysis of the HCLL Blanket Concept for the European DEMO Using the TRIPOLI-4 Monte Carlo Code
EUROFUSION CP(15)06/17 J.-C. Jaboulay et al. Nuclear Analysis of the HCLL Blanket Concept for the European DEMO Using the TRIPOLI-4 Monte Carlo Code 12th International Symposium on Fusion Nuclear Technology
More informationOverview of Pilot Plant Studies
Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology
More informationStatus of the Concept Design of CFETR Tokamak Machine
Status of the Concept Design of CFETR Tokamak Machine Tokamak Machine Design Team Presented by Songtao WU Slide 1 Outline Guideline of the Tokamak Design Magnet Configuration and Preliminary Analysis VV
More informationCFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module
EUROFUSION WPBB-CP(16) 15530 A. Tassone et al. CFD simulation of the magnetohydrodynamic flow inside the WCLL breeding blanket module Preprint of Paper to be submitted for publication in Proceedings of
More informationThermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules
EUROFUSION WPBB-CP(16) 15736 J Aubert et al. Thermo-mechanical analyses and ways of optimization of the helium cooled DEMO First Wall under RCC-MRx rules Preprint of Paper to be submitted for publication
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 informationProgress and Status of ITER Solid Breeder Test Blanket Module in in China
Progress and Status of ITER Solid Breeder Test Blanket Module in in China Presented By: Kaiming Feng (Southwestern Institute of Physics, Chengdu, China) Presented at 14th International Workshop on Ceramic
More informationHelium Catalyzed D-D Fusion in a Levitated Dipole
Helium Catalyzed D-D Fusion in a Levitated Dipole Jay Kesner, L. Bromberg, MIT D.T. Garnier, A. Hansen, M.E. Mauel Columbia University APS 2003 DPP Meeting, Albuquerque October 27, 2003 Columbia University
More informationStudies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL)
Studies of Next-Step Spherical Tokamaks Using High-Temperature Superconductors Jonathan Menard (PPPL) 22 nd Topical Meeting on the Technology of Fusion Energy (TOFE) Philadelphia, PA August 22-25, 2016
More informationDevelopment of high intensity D T fusion neutron generator HINEG
INTERNATIONAL JOURNAL OF ENERGY RESEARCH Int. J. Energy Res. (2016) Published online in Wiley Online Library (wileyonlinelibrary.com)..3572 Development of high intensity D T fusion neutron generator HINEG
More informationCharacterization of waste by R2S methodology: SEACAB system. Candan Töre 25/11/2017, RADKOR2017, ANKARA
Characterization of waste by R2S methodology: SEACAB system Candan Töre 25/11/2017, RADKOR2017, ANKARA SEA Ingeniería y Análisis de Blindajes Avda. de Atenas, 75, 106-107 28230 LAS ROZAS (Madrid) Tel:
More informationValidation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications
Validation Of COMSOL Multiphysics For Magneto-hydro-dynamics (MHD) Flows In Fusion Applications Yi Yan (yiyan@fusion.ucla.edu) Fusion Science and Technology Center, UCLA October 05, 2017 1 Introduction
More informationFusion Neutronics, Nuclear Data, Design & Analyses - Overview of Recent FZK Activities -
Forschungszentrum Karlsruhe Technik und Umwelt Fusion Neutronics, Nuclear Data, Design & Analyses - Overview of Recent FZK Activities - Ulrich Fischer Association FZK-Euratom Forschungszentrum Karlsruhe,
More informationThe FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:
The FTU facilities FTU Machine Summary of the machine operation During 2005, the machine operated at the high level of 91% of successful pulses. The experimental activity started in March and went on till
More informationTritium Inventories and Containment Philosophy for the Fuel cycle of ITER
Tritium Inventories and Containment Philosophy for the Fuel cycle of ITER I. R. Cristescu 1), I. Cristescu 1), L. Doerr 1), M. Glugla 1), D. Murdoch 2) 1), Tritium Laboratory, Germany 2) EFDA CSU Garching,
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 informationProgress and Preliminary R&D Plans of China Solid Breeder TBM
Progress and Preliminary R&D Plans of China Solid Breeder TBM K.M. Feng Presented at 13 th Ceramic Breeder Blanket Interaction Workshop Santa Barbara, CA, USA Nov. 30-Dec. 2, 2005 1 Contents I. Introduction
More informationNuclear Fusion and ITER
Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development
More informationNuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy
Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012 Fusion research is ready for the next
More informationThe Role of Multiple Effects/Interactions in a Science Based Blanket/FW R&D pathway
The Role of Multiple Effects/Interactions in a Science Based Blanket/FW R&D pathway Presented by Neil Morley Prepared by Mohamed Abdou, Sergey Smolentsev, Alice Ying, Neil Morley, Gautam Pulugundla, Cyril
More informationPresent status of fusion neutronics activity and comments to neutron diagnostics for TBM
CBBI-13: Thirteenth International Workshop on Ceramic Breeder Blanket Interactions 30 Nov 2 Dec 2005 Fess Parker DoubleTree Resort Santa Barbara, CA, USA Present status of fusion neutronics activity and
More informationThe Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory
The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal
More informationMELCOR Analysis of Helium/Water/Air Ingress into ITER Cryostat and Vacuum Vessel
TM-2926-1 MELCOR Analysis of Helium/Water/Air Ingress into ITER Cryostat and Vacuum Vessel C. H. Sheng and L. L. Spontón Studsvik Nuclear AB, SE-611 82 Nyköping, Sweden chunhong.sheng@studsvik.se Abstract
More informationNeutronics calculations for the ITER Collective Thomson Scattering Diagnostics
Neutronics calculations for the ITER Collective Thomson Scattering Diagnostics 17 th Meeting on Reactor Physics in the Nordic Countries Göteborg, Sweden May 11-12, 2015 E. Nonbøl 1, E. Klinkby 1, B. Lauritzen
More information5. Thick Liquid Blanket Concept 5.1 Introduction Ralph Moir 5.2 Idea Description and Rationale Alice Ying/ Ralph Moir/ Karani Gulec 5.2.
5. Thick Liquid Blanket Concept 5. Introduction Ralph Moir 5. Idea Description and Rationale Alice Ying/ Ralph Moir/ Karani Gulec 5.. General Perspective 5.. Applications to Tokamaks 5..3 Applications
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 information