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Fusion-triggered Liquid-phased Transmutator Monitored and Controlled Real-time by CAN Laser and Gamma beams A. Necas, T. Tajima, S. Gales, K. Hatfield, G. Mourou, M. Leroy, J. Tanner and the Entire TAE Team TAE Technologies, Inc., 19631 Pauling, Foothill Ranch, CA 92610 Motivation A Scientific Journey from Wakefields to Astrophysics and Fusion: A Symposium in Honor of Toshiki Tajima, January 25 - 26, 2018 • University of California, Irvine, Irvine, CA S. Gales (2008) Historical Flow and Confluence Fission Accelerator Fusion Laser Our Transmutator (2017) Fermi pile (1942) Molten salt reactor (1957) ADS Subcritical Reactor C. Rubbia (1995) Betatron Don Kerst (1940) Declassified (1956) Beam stabilized FRC Rostoker (2012) Invention (1960) CAN Laser (2013) Laser Compton Gamma (1990’s) Simulating Our Transmutator Compact, Safe, Mobile, Liquid TRANSMUTATOR of Spent Nuclear Waste Nuclear Waste and FLiBe solution IN CAN laser and Gamma beams monitors Vary NUCLEAR WASTE concentration by laser monitor Transmuted Nuclear Waste chemically separated and OUT FRC Fusion Neutron generator Neutral beams Field Reversed Configuration (FRC) Merge 14 MeV neutron generation Our Transmutator (our “toilet science”) : Conceptual Design MA Fission xs >> neutron capture xs for neutron energy Safe by Liquid solution-FLiBe (molten salt with very high boiling pt; passive safety valve) Safe by real-time monitor and control (by laser and laser Compton gamma) Operation close to overall criticality and yet safe (criticality varied radially by segmented tanks) Light burden on Fusion Trigger (flexibility, safety , compact, mobile, inexpensive) Low energy accelerator for Fusion trigger (compact and cheap) Fusion FRC stabilized by accelerator à Confluence of many technologies : low-energy accelerator-driven Fusion; fusion-triggered fission; safe liquid-phased MSR ; liquid MA monitored / controlled realtime by laser; realtime chemical separation in liquid r1 r2 Graphite r3 r4 Tank2: FLiBe/Am-241 Tank1: FLiBe/Cm-243 Hastelloy wall Plasma Thermal Power Generated by burning actinides =100 MW Dr r1 r2 r3 r4 GEOMETRY Dr=5 cm r1=60 cm r2=75 cm r3=90 cm r4=115 cm Tank axial length=10 m Fission xs >> neutron capture xs Cross section [barns] Neutron incident energy [MeV] NEUTRON SOURCE Plasma Axial length=8 m Radius=0.45 m Energy = 14 MeV Source @ t=0 % by volume Initial Molar % Cm-243 Am-241 LiF BeF 2 CmF 3 AmF 3 Tank 1 2% 0 63.2% 35.9% 0.9% 0.0 Tank 2 0 1% 63.5% 36.1% 0.0% 0.4% Fusion neutron energy ~14MeV Keff U, Pu (MOX) PWR U ore enriched U Pu recycling (Fr,J) U,Pu precious fuel!!! Waste: - Fission products - 0.1% Pu - 100% Np, Am, Cm - Once-through Pu recycling - possibility of multirecycling Reduction of final waste Partition &Transmutation Curtesy: S. Gales (2008) Once-through case (US,Sw): No Recycling, geological repository Nuclear Spent Fuel Radiotoxicity Transmutation reduces radiotoxicity and heat Mass depletion of Cm-243 Mass depletion of Am-241 Time [days] Time [days] Mass [kg] Mass [kg] Burnup Results using MCNP/CINDER90 and MCNP/MURE

Fusion-triggered Liquid-phased Transmutator … · segmented tanks) •Lightburden on Fusion Trigger(flexibility, safety, compact, mobile ... fusion-triggered fission; safe liquid-phased

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Fusion-triggered Liquid-phased Transmutator Monitored and Controlled Real-time by CAN Laser and Gamma beamsA. Necas, T. Tajima, S. Gales, K. Hatfield, G. Mourou, M. Leroy, J. Tanner and the Entire TAE Team

TAE Technologies, Inc., 19631 Pauling, Foothill Ranch, CA 92610Motivation

A Scientific Journey from Wakefields to Astrophysics and Fusion: A Symposium in Honor of Toshiki Tajima, January 25 - 26, 2018 • University of California, Irvine, Irvine, CA

S. Gales (2008)

Historical Flow and Confluence

Fission Accelerator Fusion Laser

OurTransmutator(2017)

Fermipile(1942)

Moltensaltreactor(1957)

ADSSubcriticalReactorC.Rubbia(1995)

BetatronDonKerst (1940)

Declassified(1956)

BeamstabilizedFRCRostoker (2012)

Invention(1960)

CANLaser(2013)

LaserComptonGamma(1990’s)

Simulating Our Transmutator

Compact, Safe, Mobile, LiquidTRANSMUTATOR

of Spent Nuclear WasteNuclear Wasteand FLiBe solutionIN

CAN laser andGamma beamsmonitors

Vary NUCLEAR WASTEconcentrationby laser monitor

Transmuted NuclearWaste chemicallyseparated andOUT

FRC Fusion Neutron generator

Neutral beams

FieldReversedConfiguration(FRC)Merge14MeVneutrongeneration

OurTransmutator (our“toiletscience”): ConceptualDesign• MAFissionxs >> neutroncapturexs forneutronenergy• Safe byLiquid solution-FLiBe (moltensaltwithveryhighboilingpt;passivesafetyvalve)

• Safe byreal-time monitor andcontrol (by laserandlaser Comptongamma)• Operationclosetooverallcriticality andyetsafe(criticalityvariedradiallybysegmentedtanks)

• Light burdenonFusionTrigger (flexibility,safety,compact,mobile,inexpensive)• LowenergyacceleratorforFusiontrigger(compactand cheap)• FusionFRCstabilized byaccelerator• à Confluenceofmanytechnologies:low-energyaccelerator-drivenFusion;fusion-triggeredfission;safeliquid-phasedMSR ;liquidMAmonitored/controlledrealtime bylaser;realtime chemicalseparation inliquid

r1

r2

Graphite

r3

r4

Tank2:FLiBe/Am-241

Tank1:FLiBe/Cm-243

Hastelloywall

Plasma

ThermalPowerGeneratedbyburningactinides=100MW

Dr

r1

r2

r3

r4

GEOMETRYDr=5cmr1=60cmr2=75cmr3=90cmr4=115cmTankaxiallength=10m

Fissionxs >> neutroncapturexs

Cro

ss s

ectio

n [b

arns

]

Neutron incident energy [MeV]

NEUTRONSOURCEPlasmaAxiallength=8mRadius=0.45mEnergy=14MeVSource@t=0

% by volume Initial Molar %Cm-243 Am-241 LiF BeF2 CmF3 AmF3

Tank 1 2% 0 63.2% 35.9% 0.9% 0.0

Tank 2 0 1% 63.5% 36.1% 0.0% 0.4%

Fusion neutronenergy ~14MeV

Keff

U, Pu (MOX)

PWR

U ore

enriched U

Pu recycling (Fr,J)

U,Pu precious fuel!!!Waste:- Fission products- 0.1% Pu- 100% Np, Am, Cm- Once-through

Pu recycling

- possibility of multirecycling

Reduction of final waste

Partition&TransmutationCurtesy:

S.Gales(2008)

Once-through case (US,Sw): No Recycling, geological repository

Nuclear Spent Fuel Radiotoxicity

Transmutation reduces radiotoxicity and heat

Mass depletion of Cm-243 Mass depletion of Am-241

Time [days] Time [days]

Mas

s [k

g]

Mas

s [k

g]

Burnup Results using MCNP/CINDER90 and MCNP/MURE