RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000. General Comments on the Development of Future Fusion PFCs presented by Richard E. Nygren Sandia National Laboratories ARIES High Heat Flux Components Workshop UCSD 10-12 December 2008
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RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company,
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RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSDSandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company,
for the United States Department of Energy’s National Nuclear Security Administration under contract DE-AC04-94AL85000.
General Comments on theDevelopment of Future Fusion PFCs
presented by Richard E. Nygren
Sandia National Laboratories
ARIES High Heat Flux Components WorkshopUCSD 10-12 December 2008
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Alternates
Tokamak/AT Focus: 1. tokamak divertors
2. solid surface PFCs
3. present/ITER-DEMO gap
Other: 4. alternates
5. liquid surface
6. other fusion pathways
BROAD SCOPE
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Alternates
Tokamak/AT ITERdivertor
TFTRTore Supra
JT-60U DIII-D
ASDEX-U
JET
TEXTOR
Non-electric or hybrid applications
Wendelstein
LHD
MAST
W7X
NSTX
BROAD SCOPE
C-MOD
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Tokamak/AT ??????
Alternates
DEMO-B divertor
ITERdivertor
JT-60U DIII-D
ASDEX-U
JET
TEXTOR
DEMO-A divertor
Non-electric of hybrid applications
Wendelstein
LHD
MAST
W7X
NSTX ???
???
?? primary alternate
C-MOD
TFTRTore Supra
???/CTF
BROAD SCOPE
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Tokamak/AT ??????
Alternates
DEMO-B divertor
ITERdivertor
TFTRTore Supra
JT-60U DIII-D
ASDEX-U
JET
TEXTOR
DEMO-A divertor
Non-electric of hybrid applications
Wendelstein
LHD
MAST
W7X
NSTX ???
???
?? primary alternate
?liquid surface
C-MOD
good efficiency high availability damage resistance
D/T plasma solid surface long pulse
???/CTF
BROAD SCOPE
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Tokamak/AT ??????
DEMO-B divertor
ITERdivertor
TFTRTore Supra
JT-60U DIII-D
ASDEX-U
JET
TEXTORgood efficiency high availability damage resistance
D/T plasma solid surface long pulse
DEMO-A divertor
???/CTF
GAP 1GAP 2
WORKSHOP SCOPE
C-MOD
high temperature high reliability neutron damage
tritium retentionactive cooling
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
high temperature high reliability neutron damage
active cooling tritium retention
GAP 1GAP 2
WORKSHOP SCOPE
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
GAP XGAP Y
physics
Tech.
tokamak
Alt’s.
high temperature high reliability neutron damage
active cooling tritium retention
GAP 1GAP 2
OTHER SCOPE
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Tokamak/AT ??????
DEMO-B divertor
ITERdivertor
TFTRTore Supra
JT-60U DIII-D
ASDEX-U
JET
TEXTOR
DEMO-A divertor
C-MOD
D Maisonnier et al., DEMO and Fusion Power Plant Conceptual Studies in Europe Nucl. Fusion 47 (2007) ISFNT7
K. Lackner SOFT2006
G Federici et al.,Key ITER plasma edge and plasma–material interaction issues, JNM 313–316 (2003) PSI
J Linke et al., High heat flux testing of plasma facing materials …, JNM 367–370 (2007)
V PhilippsPlasma–wall interaction, a key issue on the way to a steady state burning fusion device, Phys. Scr. T123 (2006)
SOURCES
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Tokamak/AT ??????
DEMO-B divertor
ITERdivertor
TFTRTore Supra
JT-60U DIII-D
ASDEX-U
JET
TEXTOR
DEMO-A divertor
C-MOD
D Maisonnier et al., DEMO and Fusion Power Plant Conceptual Studies in Europe Nucl. Fusion 47 (2007) ISFNT7
K Lackner SOFT2006
G Federici et al.,Key ITER plasma edge and plasma–material interaction issues, JNM 313–316 (2003) PSI
J Linke et al., High heat flux testing of plasma facing materials …, JNM 367–370 (2007)
V PhilippsPlasma–wall interaction, a key issue on the way to a steady state burning fusion device, Phys. Scr. T123 (2006)
D Whyte The Challenges of Plasma-Surface Interactions for ITER & Beyond, to FESAC Nov 2008
“Greenwald” Panel Report Priorities, Gaps and Opportunities: Towards A Long-Range Strategic Plan For Magnetic Fusion Energy, FESAC Oct 2007
US ReNew Activity
Sources
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
“The themes were defined in terms of knowledge required prior to Demo. ... based on sound scientific principles and rigorously tested in the laboratory so that the step to a [DEMO] .. taken with high confidence of success.
“Greenwald” Panel Report
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Theme B. Taming the Plasma Material Interface:
.. knowledge sufficient to design and build, with high confidence,
8. PWI: Understand and control of all processes that couple the plasma and nearby materials.
9. PFCs: Understand .. materials and processes that can be used to design replaceable components that can survive ..
10. .. Other .. : .. necessary understanding of plasma interactions, neutron loading and materials to allow design of .. any other diagnostic equipment that can survive ...
“The themes were defined in terms of knowledge required prior to Demo. ... based on sound scientific principles and rigorously tested in the laboratory so that the step to a [DEMO] .. taken with high confidence of success.
“Greenwald” Panel Report
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
Theme C. Harnessing fusion power:
knowledge .. sufficient to design and build, with high confidence,
11. Fuel Cycle: .. manage the flow of tritium ...
12. Power: .. temperatures sufficiently high for efficient production of electricity or hydrogen.
13. Materials ..: Understand the basic materials science for fusion breeding blankets, structural components, plasma diagnostics and heating components .. high neutron fluence ..
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
“Greenwald” Panel ReportFinding 6. Evaluation of current and planned
programs and summary of gaps….. The most significant gaps were: G1. …. G2. …G-5. Ability to predict and avoid, or detect and mitigate,
off-normal plasma events …G-9. Sufficient understanding of all plasma-wall interactions ….
The science underlying the interaction of plasma and material needs to be significantly strengthened to ..
G-10. Understanding of the use of low activation solid and liquid materials, joining technologies and cooling strategies ...
G-11. Understanding .. the complete fuel cycle, particularly ..G-12. An engineering science base .. effective removal of heat ...G-13. Understanding .. low activation materials .. G-14. .. guarantee safety over the plant life cycle - including ..G-15. .. efficient maintainability of in-vessel components ..
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
“Greenwald” Panel Report
Recommendation 4. .... nine major initiatives.
I-1. .. predictive plasma modeling and validation ..,
I-2. Extensions to ITER AT capabilities .. burning AT regimes
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
D Whyte FESAC Presentation“The Challenges of PSI for ITER & Beyond” Nov 2008
Quiescent energy exhaust
Transient energy exhaust from plasma instabilities
Yearly neutron damage in plasma-facing materials
Max. gross material removal rate with 1% erosion yield
Tritium consumption
Issue/Gap tokamaks ITER CTF DEMO now
greatly increasing
parameters
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
D Whyte FESAC Presentation“The Challenges of PSI for ITER & Beyond” Nov 2008
Lack basic understanding and diagnosis of PSI processes in fusion devices → Uncertain extrapolation
Heat exhaust is primary design point for edge materials, since this Is directly related to fusion power density
Thermal efficiency .. high ambient T → Fundamentally different Physical Chemistry .. completely unexplored in fusion
devices Energy sustainment chasm to CTF & DEMO Rapid dissipation of plasma thermal energy poses major
challenges in any Demo consequences of large particulate removal on .. plasma .. & safety Tokamak edge plasmas feature extreme spatial gradients and
fluctuations levels, .. erosion prediction & control very difficult
It is hard to overstate the importance of ambient temperature for fuel control & T retention
30+ years of experience .. we should be worried/excited .. in particular the effects of having “hot walls”
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSDPower plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7]
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSDPower plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7]
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSDPower plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7]
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSDPower plant conceptual studies in Europe D. Maisonnier, D. Campbell, I. Cook, Nucl. Fusion 47 (2007) 1524–1532 [ISFNT7]
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
High temperature He-cooled divertor
Need for work on divertor systems
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
In contrast to the rest of the world, a typical preference of US technology people has been
one step to high tech DEMO (reactor prototype)
parallel R&D for materials and blankets (CTF)
Whose DEMO?
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
In contrast to the rest of the world, a typical preference of US technology people has been
one step to high tech DEMO (reactor prototype)
parallel R&D for materials and blankets (CTF)
Whose DEMO?
We have a great challenge to develop the needed
technology!
ITER activity is a revealing as we observe
the need for definition and integration in the design
along with the need to move forward in building the
machine!
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD J. Linke et al., JNM 367–370 (2007) 1422–1431
We develop PFCs using single effects tests
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
We are good at developing issuesWe tend to
be optimistic (we are in fusion after all)
enjoy identifying issues and pondering problems
look toward R&D programs
Hey – nice
issu
e
Congratulations on your new issue.
You rAPER Raised some important issues I
We love issues
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
GAP 3: Technology Culture
testsMaterial B
Material Aproperties 2
joining
properties
mockups prototypestests tests
prototypes
rad effects testing
PFC tests
PWI tests
Material A tokamak couponslab tests lab tests
test PFC
design validation
manufacturingdevelopment
QA development
scale upVendor qual.
manufacturingacceptance
components
PWI & PFC tests component dev./qual
M a t ’l s d e v el o p m e n tWe develop
one-of-a kind units with anecdotal mockup tests.
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
A realistic “fully funded” technology
program, will involve a strong winnowing
of choices
for PFC materials and divertor technology
simply because of the time to develop and
prove
specific robust components for a DEMO.
GAP 3: Technology Culture
Configuration d e v e l o p m e n t
PWI & PFC tests component dev./qual
M a t ’l s d e v e l o p m e n t
STs, others Ergodic div.Super-X div. Liquid PFCs
RE Nygren, Sandia ARIES Town Hall - 10-12dec2008 - UCSD
PROGRAM & DESIGN INTEGRATIONknowledge .. sufficient to design and build, with high confidence,
Recall some excerpts from the “Greenwald” panel report:
9. PFCs: Understand .. materials and processes … design replaceable components that can survive ..