1/18 RE Nygren ReNeW White Paper: Strong Sustained Integrated HHFC Modeling & Testing -- March 2009,...

1/18 RE Nygren ReNeW White Paper: Strong Sustained Integrated HHFC Modeling & Testing -- March 2009, UCLA

Future Plasma Facing Components (PFCs) & In-vessel Components (IVCs):

The Need for a

Strong Sustained & Integrated Approach for Modeling and

Testing

R.E. NygrenFusion Technology Department

Sandia National Laboratories• Deputy Director, Virtual Laboratory for Technology

• Member, Power Extraction Subpanel in HFP

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.

Presentation at the ReNeW Joint Workshop 2-6 March 2009 for the themes of Harnessing Fusion Power and Taming the Plasma Interface


Gaps & Needs (“Greenwald” Panel)

Compelling schedule for actively-cooled PFCs and IVCs

Proposal: emphasize and include strong sustained & well integrated program in technology in thrusts for PFCs, IVCs, PMI, Power Extraction, … others that starts now!

OUTLINE High Heat Flux Components include

Plasma Facing Components and some

In-Vessel Components


An HHFC Program – Guiding Principles

At each of the stages of development toward a DEMO there is a critical set of capabilities in fusion nuclear technology that need to be in place to proceed further.

Progress will occur through a well integrated program of computational models and benchmark experiments, (well instrumented) first in labs, later in dedicated facilities.

We (fusion) require authoritative information on technology to identify paths toward a successful DEMO.

This in turn requires an understanding informed by in-depth studies of possible design alternatives and

enabling technologies, integrated predictive modeling of PFC/IC performance, and supporting experiments.


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 lab so that the step to a [DEMO] .. taken with high confidence of success.”

“The Report also characterized PFCs and materials as “Tier 1 solution not in hand, major extrapolation ..”

“Greenwald” Panel Report


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 ..

14. Safety: Demonstrate .. safety …. minimize environmental burdens ..

15. RAMI [Reliability, Availability, Maintainability & Inspectability]: Demonstrate .. productive capacity …. validate economic assumptions ….



“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 ..



Recommendation 4. .... nine major initiatives.

I-1. .. predictive plasma modeling and validation ..,

I-2. Extensions to ITER AT capabilities .. burning AT regimes

I-3. Integrated advanced burning physics …facility .. dedicated

I-5. .. disruption-free concepts .. performance extension device ..

I-6. .. advanced computer modeling and laboratory testing .. single-effects science for major fusion technology issues,

I-8. Component development/testing program … multi-effect issues in critical technology .. breeding/blanket .. first wall

I-4. Integrated experiment for PWI/PFCs .. steady-state .. non-DT

I-7. Materials qualification facility … (IFMIF). I-9. Component qualification facility.. high availability.. heat

flux .. neutron fluence .. DT device .... (CTF).


Current Status of HHFC Program Excluding PMI and edge programs

edgemodeling

PMI modeling& testing

PFC & IVC operations

HHFC modeling& testing

#1

3. Develop and prove robust PFCs for future confinement devices.

limited but sustained work on He cooled W and on liquid surfaces

gap: expanded test capabilities; stronger integrated modeling; test capabilities (He, liq. met.)

Support ITER PFC design & R&Dand develop component fabrication processes, QA, and operation.

excellent relations with IPO, IP, DAs; US R&D & testing (for all DAs) ongoing; US role in design expanding; valuable insight into design/machine interfaces

gap: test capabilities (old & frail); design integration & interfaces; participation in divertor R&D

2. Support physics missions of existing, upgraded and new US confinement experiments.

current need but little R&D [NSTX Liquid Li divertor is really PMI]

gap: program organization; integration with machines; test capabilities (He,

probes, disruption simulation)

MAU

DLY


An HHFC Program to address the gapsIntegrated with PMI models & tests, edge modeling, and operations

Well integrated technology program:

Supporting HHF tests & other experiments:

Comprehensive confirmed predictive models:

Development of instrumentation:

component development

extensive instrumentation

robust actively-cooled PFCs & IVCs - design confirmation

[modeling, testing]- fabrication (?dev.) - QA & acceptance



Well integrated technology program: support ongoing physics missions and future devices with strong integration and coordination with devices, PMI and edge.

Supporting HHF tests & other experiments:confirm performance and enable deployment of new PFCs & IVCs

Comprehensive confirmed predictive models: PMI, edge plasmas, thermal-hydraulics, materials behavior

Development of instrumentation: needed for safe operation and to evaluate performance; “smart tiles,” actively-cooled PFCs and IVCs (and TBMs, etc.)





DIII-D, C-MOD, NSTX,Upgrades,ITER, CTF, DEMO



Comprehensive and predictive models: PMI, edge plasmas, TH & mat’ls behavior

Supporting HHF & other experiments: confirm performance, enable deployment of new PFCs/IVCs in & future devices

Well integrated technology program: support ongoing physics missions and future devices …

Development of instrumentation: actively-cooled PFCs/IVCs (+TBMs,..), “smart tiles”, probes, …





Partnership of modelers & experimenters & PFC users e.g., critical roles of test design and measurements

Technologists understand machine interfaces & req’mts

Existing “work horse” lab facilities need upgrades, expansion and support







Fundamental Point 1:

HHFC R&D is challenging & time-consuming. It requires strong coordination with confinement projects on interfaces and with industrial suppliers on fabrication development, QA and acceptance.


Fundamental Point 1:

HHFC R&D is challenging & time-consuming. It requires strong coordination with confinement projects on interfaces and with industrial suppliers on fabrication development, QA and acceptance.






~25y - fusion-specific water-cooled heat sinks

~15y - ITER PFC R&D ~10y detailed R&D ITER design changing ~ 4y FWQ mockups ?US vendors engaged 3-5y final design to fab

Tore Supra water cooled PFCs modular limiters in 1990s failed very good history working closely

with Plansee on fabrication yet still had quality problems rebuilt PFCs - CIEL completed 2002

FWQM Testing StatusUS & EU MockupsDate: End of May 8, 2008Cycles Completed: 3447


J. Linke et al., JNM 367–370 (2007) 1422–1431

We develop PFCs using single effects tests

Testing Hierarchy

ITER & CTF for “integrated” tests.

HHFC/PMI facilities for single & multiple effects.

These “work horse” lab facilities will continue and need upgrades, expansion & sustained support.


Fundamental Point 2: A strong well integrated HHFC program (near term) could enable new PFCs and IVCs in upgrades for longer shots, higher power or hot walls. Consider deploying He-cooled probes or guards to postpone water cooling. Cooling with room temperature He (not high T, lower density) is a less challenging adaption of the technology.







Fundamental Point 2: A strong well integrated HHFC program (near term) could enable new PFCs and IVCs in upgrades for longer shots, higher power or hot walls. Consider deploying He-cooled probes or guards to postpone water cooling. Cooling with room temperature He (not high T, lower density) is a less challenging adaption of the technology.

Heat pipes and helium cooling technology have both progressed significantly in the last decade.






3.2 cm

1.3 cm ID

1.9 cm

W F

oam

Heat E

xchan

ger

CV

D W

Tu

be

CV

D N

bB

on

d Jo

int

(Metallu

rgical B

on

d)

2.0 cm

15.2 cm

Mach

ined

Nb

Tu

be

Fo

r Sw

agelo

kJo

int

3.2 cm

1.3 cm ID

1.9 cm

W F

oam

Heat E

xchan

ger

CV

D W

Tu

be

CV

D N

bB

on

d Jo

int

(Metallu

rgical B

on

d)

2.0 cm

15.2 cm

Mach

ined

Nb

Tu

be

Fo

r Sw

agelo

kJo

int

US He-cooled PFC target >20MW/m2


Focus: 1. tokamak divertors2. solid surface PFCs 3. present/ITER-DEMO gap

Other: 4. alternates5. liquid surface6. other fusion pathways

Alternates

Tokamak/AT

Non-electric or hybrid applications

Compelling schedule for actively-cooled HHFCs


Alternates

Tokamak/AT ???

DEMO-B divertor

ITERdivertor

JT-60U DIII-D

ASDEX-U

JET

TEXTOR

DEMO-A divertor

Non-electric or hybrid applications

Wendelstein

LHD

MAST

W7X

NSTX ???

???

?? primary alternate

C-MOD

TFTRTore Supra

???

???

ReNeW PFCs

???/CTF


???

Alternates

Tokamak/AT ???

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 ???

???


?liquid surface

C-MOD

ReNeW PFCs

???

good efficiency high availability damage resistance

D/T plasma solid surface long pulse


???

???

Alternates

Tokamak/AT DEMO-B divertor

ITERdivertor

TFTRTore Supra

JT-60U DIII-D

ASDEX-U

JET

TEXTOR

DEMO-A divertor


Wendelstein

LHD

MAST

W7X

NSTX ???

???


C-MOD

ReNeW PFCs

high temperature high reliability neutron damage

tritium retentionactive cooling



GAP 1GAP 2

?liquid surface


???

Alternates


ITERdivertor

TFTRTore Supra

JT-60U DIII-D

ASDEX-U

JET

TEXTOR

DEMO-A divertor


Wendelstein

LHD

MAST

W7X

NSTX ???

???


C-MOD

ReNeW PFCs





GAP 1GAP 2

?liquid surface

???/CTF

???


???

Alternates


ITERdivertor

TFTRTore Supra

JT-60U DIII-D

ASDEX-U

JET

TEXTOR

DEMO-A divertor


Wendelstein

LHD

MAST

W7X

NSTX ???

???


C-MOD

ReNeW PFCs





GAP 1GAP 2

?liquid surface

??? orupgrade

engineeringinstrumentation

actively cooledlaunchers,

probes (IVCs) ???/CTF

Analog thinker in a digital age.


E N D



At each of the stages of development toward a DEMO there is a critical set of capabilities in fusion nuclear technology that need to be in place to proceed further.

Progress will occur through a well integrated program of computational models and benchmark experiments, (well instrumented) first in labs, later in dedicated facilities.

We (fusion) require authoritative information on technology to identify paths toward a successful DEMO.

This in turn requires an understanding informed by in-depth studies of possible design alternatives and

enabling technologies, integrated predictive modeling of PFC/IC performance, and supporting experiments.


We will need to proceed through several stages of readiness in PFCs, ICs and all of FNST to build a DEMO.

1st stage development: minimum set of capabilities to support the understanding of science-based engineering principles


Experimental facilities with hot fluids and hot walls and adequate instrumentation

Integrated computational models

Appropriate materials

Appropriate experience with design integration and safety


Development of PFCs and In-vessel Components for upgrades and new devices

Preparation of initial integrated experiments in ITER, i.e., TBMs and appropriate instrumentation

Serious evaluations of possible designs for a CTF-type device and for the supporting effort to develop components

Decisions about successful paths for future devices (e.g., upgrades, D/D and D/T CTFs and DEMO)


The first level of readiness enables the following activities:

1/18 RE Nygren ReNeW White Paper: Strong Sustained Integrated HHFC Modeling & Testing -- March 2009,...

Documents

Transcript of 1/18 RE Nygren ReNeW White Paper: Strong Sustained Integrated HHFC Modeling & Testing -- March 2009,...