Developing a Vendor Base for Fusion Commercialization

Stan Milora, DirectorFusion Energy DivisionVirtual Laboratory of

TechnologyMartin Peng

Fusion Energy Division

Relationship of Initiatives to Gaps (2007 FESAC Greenwald Panel)

-------- Fusion Nuclear S&T --------

--------- Plasma Control S&T ---------

Ed Synakowski, Associate DirectorOffice of Fusion Energy SciencesFebruary 28, 2012

US Industry already being engaged to design and build major ITER components (ORNL, PPPL, SRNL)

Cooling, Diagnostics, Plasma Heating, Fueling and Exhaust Systems (Tritium), Electrical Network, S/C Magnets

5 Managed by UT-Battellefor the U.S. Department of Energy Juergen Rapp, Presentation to DOE, December 8th 2011

Challenge: particle fluxes and fluence

JET ITER Fusion Reactor

50 x higher ion fluxes

5000 x higher ion fluence

106 x higher neutron fluence (~1dpa)

up to 5 x higher ion fluence

100 x higher neutron fluence (~150 dpa)

Plasma facing components encounter 20% of the fusion energy release as high surface heat and ion fluxes.

• High average and transient heat fluxes

• Surface ablation and melting .

• Erosion and re-deposition, dust formation, and plasma contamination

• Tritium implantation and retention strongly coupled to neutron damage

Plasma facing components in JET and NSTX: first wall (A), rf antenna (B), and divertor (C)

A

B

C

B

B

Tritium breeding and power extraction components volumetrically absorb 80 % of the fusion energy release via nuclear materials interactions.

ITER dual cooled lead lithium (DCLL) tritium breeding test blanket concept

PbLi out

He outHe in

PbLi in

Be first wall

Reduced Activation Ferritic/Martensitic Steel(RAFM) structure

Depth in DCLL TBM(cm)Nuclear/materials interaction in RAFM

Po

we

r D

en

sit

y(W

/cm

3 )

• High temperature creep, thermo mechanical and magnetic stresses, corrosion

• Thermo fluid flow and conducting fluid flow across magnetic fields

• Tritium production, release, extraction and control

• Hardening, loss of ductility and fracture toughness, thermal conductivity degradation

• Void swelling, helium embrittlement

• Activation

New ceramic materials and radiation-resistant steels with superior high-temperature strength for use in prototype fusion reactors have been developed.

Type S Nicalon silicon carbide composite demonstrates stability of strength to70 dpa irradiation @ 800 degrees C

14-YWT oxide dispersion strengthened steeldemonstrates stability of dispersion

to 100 dpa irradiation @ 600 degrees C

100 nm

HFIR Atomic Probe Microscope

Strategy

Leadership areas

Infrastructure • Plasma Materials Test Stand (PMTS) to simulate FNSF plasma−surface conditions

• Establish scientific basis for materials behavior in a fusion environment, tritium breeding, and reliable and efficient power extraction

• Outcome: Facilitate transition from fusion physics to fusion engineering and from non-nuclear to full nuclear systems

High-performance, radiation-resistant

ODS steels

• Fission and spallation neutron sources• Plasma control technologies• Computational fusion research• Materials science and engineering• Nuclear science and technology• National and international collaborations

Develop an understanding of mission need for a next-generation Fusion Nuclear Science Facility (FNSF) that incorporates materials needs for fusion and advanced fission

Develop and execute aggressive programs to resolve scientific and technical issues for materials and the plasma–surface interface

Lead technical and programmatic planning for FNSF

Fusion S&T in the ITER era

Vision

PMTS

• Strong expertise in RF-technology, science and RF-plasma sources

• World class material science

• Experience with large scale nuclear facilities (HFIR)

• Excellence in DOE Science research users’ facilities (SNS)

• World leading computational center (Jaguar, Kraken)

• U.S. ITER Project

• Strong national and international collaborations (ASIPP and Juelich)

ORNL: capable, experienced, readyto support fusion commercialization