Multiple Effect / Multiple Interaction Discussion Topics  How do we really simulate volumetric heating in LMs without distorting the experiment? Simulate.

Slides:



Advertisements
Similar presentations
Glenn Bateman Lehigh University Physics Department
Advertisements

PHOENICS Based Arc Models as a Test Tool
Fusion Nuclear Science and Technology (FNST) Challenges and Facilities on the Pathway to Fusion Energy Mohamed Abdou Distinguished Professor of Engineering.
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
Hongjie Zhang Purge gas flow impact on tritium permeation Integrated simulation on tritium permeation in the solid breeder unit FNST, August 18-20, 2009.
Ss Hefei, China July 19, 2011 Nuclear, Plasma, and Radiological Engineering Center for Plasma-Material Interactions Contact: Flowing.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
The Reversed Field Pinch: on the path to fusion energy S.C. Prager September, 2006 FPA Symposium.
Thermo Fluid Design Analysis of TBM cooling schemes M. Narula with A. Ying, R. Hunt, S. Park ITER-TBM Meeting UCLA Feb 14-15, 2007.
What is Dual Coolant Blanket? Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University of California, Los.
HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010.
Physics of fusion power Lecture 14: Anomalous transport / ITER.
FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.
Thermo-fluid Analysis of Helium cooling solutions for the HCCB TBM Presented By: Manmeet Narula Alice Ying, Manmeet Narula, Ryan Hunt and M. Abdou ITER.
P09451 Thermo-Electric Module for Large Scale Systems Bryan McCormick-ME(Team Lead) Andy Freedman- ME John Kreuder- ME Jon Holdsworth- EE Gabriela Santa.
Physics of fusion power Lecture 8: Conserved quantities / mirror / tokamak.
Summary of Current Test Plan for US DCLL TBM in ITER Neil Morley and the US TBM Participants INL, August
FNSF Testing Strategy Discussions for PFC – PFC/FNSF Joint Session Chairs: Maingi, Menard, Morley Session Objectives and First Wall Testing Description.
LH2 Absorber Heat Load and Homeostasis. What has happened before… 1.Huge LH2 volumes, low heat deposition: Bubble chambers 2.Small LH2 volumes, low heat.
THERMOFLUID MHD for ITER TBM. CURRENT STATUS By UCLA Thermofluid MHD GROUP Presented by Sergey Smolentsev US ITER TBM Meeting UCLA May 10-11, 2006.
June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)
Multiple effects for HT DCLL Presented by Neil Morley University of California, Los Angeles US-EU DCLL Workshop November 14-15, 2014 Slides from my colleagues.
Role of ITER in Fusion Development Farrokh Najmabadi University of California, San Diego, La Jolla, CA FPA Annual Meeting September 27-28, 2006 Washington,
Thermofluid MHD issues for liquid breeder blankets and first walls Neil B. Morley and Sergey Smolentsev MAE Dept., UCLA APEX/TBM Meeting November 3, 2003.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
The effect of the orientations of pebble bed in Indian HCSB Module Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept.
Fluid Dynamics and Heat Transfer in a Hartmann Flow RPI Master’s Project Proposal Timothy DePuy – 9/28/2010.
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
Strawman R&D Tasks and R&D Costs Neil Morley and Alice Ying INL, August
Developing a Vendor Base for Fusion Commercialization Stan Milora, Director Fusion Energy Division Virtual Laboratory of Technology Martin Peng Fusion.
Fusion-Fission Hybrid Systems
Fusion: Bringing star power to earth Farrokh Najmabadi Prof. of Electrical Engineering Director of Center for Energy Research UC San Diego NES Grand Challenges.
MHD Modeling and Experiments at UCLA for the ITER Test Blanket Program N. Morley, M. Abdou, A. Ying, S. Smolentsev, M-J. Ni, T. Sketchley, J. Burris, M.
Microwave Power and Electromagnetic Energy Microwave Heating of Metal.
Managed by UT-Battelle for the Department of Energy Stan Milora, ORNL Director Virtual Laboratory for Technology 20 th ANS Topical Meeting on the Technology.
ARIES “Pathways” Program Farrokh Najmabadi University of California San Diego ARIES brainstorming meeting UC San Diego April 3-4, 2007 Electronic copy:
MHD/Heat Transfer considerations for SiC FCI in DEMO and ITER Sergey Smolentsev DCLL Special Meeting at UCLA April 23-24, 2007.
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
DIII-D SHOT #87009 Observes a Plasma Disruption During Neutral Beam Heating At High Plasma Beta Callen et.al, Phys. Plasmas 6, 2963 (1999) Rapid loss of.
2 nd EU-US DCLL Workshop University of California, Los Angeles, Nov th, 2014.
Compact Stellarator Approach to DEMO J.F. Lyon for the US stellarator community FESAC Subcommittee Aug. 7, 2007.
US Test Blanket Module Partially Integrated Testing Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for.
An ITER-TBM Experimental Thrust for ReNeW Themes III and IV Neil B. Morley, Mohamed Abdou, Alice Ying (UCLA); Mohamed Sawan, Jake Blanchard (UW); Clement.
Materials Integration by Fission Reactor Irradiation and Essential Basic Studies for Overall Evaluation Presented by N.Yoshida and K.Abe At the J-US Meeting,
045-05/rs PERSISTENT SURVEILLANCE FOR PIPELINE PROTECTION AND THREAT INTERDICTION Technical Readiness Level For Control of Plasma Power Flux Distribution.
Various Strategies for DCLL in the US Technology Program Poor ITER utilization (Lowest Cost Scenario) - Support EU HCLL effort, no independent DCLL TBM.
Review of Thermofluid / MHD activities for DCLL Sergey Smolentsev & US TBM Thermofluid/MHD Group 2006 US-Japan Workshop on FUSION HIGH POWER DENSITY COMPONENTS.
Comments on Fusion Development Strategy for the US S. Prager Princeton Plasma Physics Laboratory FPA Symposium.
Some slides on UCLA LM-MHD capabilities and Preliminary Incompressible LM Jet Simulations in Muon Collider Fields Neil Morley and Manmeet Narula Fusion.
Top-Level Technical Issues for FNST #3 MHD Thermofluid Phenomena and Impact on Transport Processes in Electrically Conducting Liquid Coolants/Breeders.
Fuel Cycle Research Thrust Using A Full Fusion Nuclear Environment
DCLL Thermofluid/MHD R&D Sergey Smolentsev, Neil Morley and the ITER- TBM thermofluid group US ITER-TBM Meeting August 10-12, 2005 INEL.
Nuclear fission Nuclear fission: heavy nuclei split into two smaller parts in order to become more stable proton neutron Kr-90 nucleus U-235 nucleus energy.
Material System Thermomechanics Interactions (cont’d) International Collaboration: Role / Impact / Recognition - Serves a unique role in IEA program on.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
HARNESSING FUSION POWER POWER EXTRACTION Power Extraction Panel Preliminary Research Thrust Ideas Robust operation of blanket/firstwall and divertor systems.
Thermal-hydraulic analysis of unit cell for solid breeder TBM
US Participation in the
DCLL TBM Reference Design
Produktentwicklung und Maschinenelemente
Summary of session 5: Innovative Ideas and New R&D
Integrated Modeling Approach and Plans
Global Warming Problem
VLT Meeting, Washington DC, August 25, 2005
Mohamed A. Abdou Summary, Approach and Strategy (M. Abdou)
An ITER-TBM Experimental Thrust for ReNeW Themes III and IV
TRL tables: power conversion and lifetime
Nuclear Analyses for two “Look-alike” HCPB Blanket Sub-modules for Testing in ITER Mahmoud Z Youssef UCLA Presented at ITER-TBM4 Meeting, UCLA, March 2-4,
TITAN - Flow Control and Thermofluid Modeling Tasks
Presentation transcript:

Multiple Effect / Multiple Interaction Discussion Topics  How do we really simulate volumetric heating in LMs without distorting the experiment? Simulate the temperature gradients –Exploring ways to producing temperature gradients with only surface heating (H lamp, graphite, radiative) –Ideas beyond embedded heaters, in wall, FCI or flow –Do we need to do MHD simulations with immersion heaters to look at flow and transport distortion –Comment was made that a gamma source could do this. What kind of power is typical? Short attenuation in Pb –Induction heating, skin depth and unintentional stirring –Microwaves for ceramic breeder, in resonant cavity 1

Near term, volumetric heating and temperature gradient  Brainstorming session for near term expeirments 2

Multiple Effect / Multiple Interaction Discussion Topics  Morley emphasized thermofluid MHD aspects as one facility. Angel commented that effects of ionizing radiation is also important to transport e.g. surface effects –In US we have discussed some ideas for fission reactor tests as complementary (small flow loop into fission reactor) –What other options are available? Gamma source –Tritium/deuterium –Separate effect test to augment multi effect, SNL, ATR, HFIR, EU 3

Multiple Effect / Multiple Interaction Discussion Topics  Very near term thermofluid MHD experiments can be done in upgraded UCLA facility. –Brainstorming on heating methods for near term volumetric heat and temperature gradient simulation –More specific hardware needs and upgrade costs should be developed –Some hardware might be useful for both EU and US test facilties – recuperators, instrumentation  Study of next generation test strategy and facility –Strategy to do the experiments –Cost and capability tradeoffs 4

What are the principal challenges in simulating the fusion nuclear environment?  Nuclear heating in a large volume with strong gradients, not possible to reproduce in simulation facility. Use various techniques Embedded heaters in LM, on walls or in flow channel inserts. Must be careful about changing the flow, FCI behavior, etc. Integration into multiple experiments required Inlet temperature control (e.g. flow in hot, let cool)  Complex magnetic field with toroidal field / poloidal field fidelity or transient fields during disruptions Requires complex magnet systems, very important for LM blankets Or utilization of modules in long pulse confinement devices  Complex mockup configuration with prototypic size and scale Not possible in fission reactors 5 Can not bring together all conditions in one test or adequately simulate nuclear heating