Transcript The Archimedes Filter John R Gilleland

The Archimedes Filter
John R Gilleland
Hanford Site Location
WTP
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Potential Location of Archimedes Filter Plant at Hanford
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Hanford Tank Waste is Extremely Challenging to Process
• Hanford tanks hold 53 million gallons of Defense
Waste:
–
–
–
26 wt% sludge
44 wt% saltcake
30 wt% supernatant
• Archimedes is focused on the sludge fraction, the
most challenging to process
–
–
chemical complexity with different past operations
and subsequent mixing
significant variability from batch to batch
• Hanford has planned an aggressive campaign to
chemically separate this material in order to reduce
the volume of waste that must be vitrified as High
Level Waste (HLW) glass.
• There is great uncertainty and practical limits to the
effectiveness of chemical separations due to:
–
–
–
–
–
–
–
waste inventory uncertainty
batch sampling uncertainty
chemical processing times
processing temperatures required
unintended chemical reactions
recycle streams
additional waste generated from added agents, etc.
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Hanford ORP Solids Dissolution Targets Result in IHLW Reduction
Archimedes Offers an Alternative for Even Greater Reduction
HLW Glass Estimates (MT)1
300,000
200,000
100,000
0
Tank Inventory Estimate
HLW Solids:
HLW Glass*:
84,403 MT
272,000 MT
Water Washing
Caustic Washing
17,553 MT
73,000 MT
10,100 MT
46,100 MT
Oxidative Leaching
9,858 MT
3 4,676 MT (ORP “revised target”)
• Hanford’s baseline targets dissolution of ~90% of the tank HLW oxides to yield an
inventory of 9,860 MT solids to be sent to vitrification, producing 34,676 MT of
HLW glass and take 22 years to process.2
*Notes: (1) HLW glass production assumes ORP’s “relaxed” glass model.
(2) Assumes 6 MTG/day with 70% utilization for HLW Vit and 1.1 MT oxide/day per Archimedes Filter with 70% utilization.
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Archimedes Approaches the Problem from a Physics Perspective
Separating HLW Oxides Based on Atomic Mass
Hanford HLW Solids
•
•
(17,553 MT “Water Washed Solids”
Inventory)
Archimedes Filter Separates “heavy”
from “light” ions.
This effectively separates radioactive
from non-radioactive elements.
•
The Filter could isolate 99.9% of the
radioactivity in just 10% of sludge mass.
•
Thus, deployment of Archimedes at
Hanford enables up to 90% of the HLW
sludge to be treated as Low Activity
Waste.
•
Separation of ions in plasma is
relatively indifferent to the chemical
complexity of waste feed.
Waste Mass
Heavy
Fraction
AMU
89
Light
Fraction
Radioactivity
99.9%
10%
90%
0.1%
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Company Mission
• From the time of its founding in 1998 Archimedes’ primary corporate
mission has been the development of a breakthrough separations
technology for treatment of high level waste from nuclear weapons
production.
• A new invention, called the “Archimedes Filter,” promises to reduce the
required number of HLW canisters at Hanford by up to 85%.
• Archimedes has raised $100 million dollars of private funds to insure
speed, flexibility and IP ownership necessary to support this mission.
• An international team of 12 institutions supports the Filter technology
development as well as associated systems development, plant design
and licensing work for US waste site applications.
• Archimedes now believes that our development of plasma based
separation represents a platform technology that may be applied to
commercial endeavors such as spent fuel recycling.
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Archimedes Team Has Deep Domain Expertise
•
Archimedes has attracted a world-class team of physicists, chemists, and engineers, including:
Tihiro Ohkawa
John Gilleland
Larry Papay
Richard Freeman
Leigh Sevier
Stephen Agnew
Sergei Putvinski
•
-
Scott Tierney, President and Chief Operating Officer, former Morgan Stanley investment banker
Industry Consultants
-
•
David Gerson, Vice Chairman of Archimedes is also Executive Vice President of the American Enterprise
Institute and a former Associate Director of the White House Office of Management and Budget (OMB)
Daniel Evans, Director of Archimedes, former United States Senator and Governor of the State of Washington
John Wagoner, Vice President of Archimedes, former DOE Hanford Site Manager (1990-1999)
Business
-
•
Vice Chairman, General Atomics Company
Chief Scientist and VP Commercial Programs, Bechtel
SVP, SAIC, Bechtel and Southern California Edison
General Atomics Company, RF Physics
General Atomics, Princeton, Plasma Systems
Los Alamos Chemical Sciences Division
International Thermonuclear Experimental Reactor
Government Relations
-
•
Chairman
CEO
Senior VP
VP Science & Tech. Dev.
VP Engineering
Senior Chemist
Senior Physicist
Harold Forsen, former VP Bechtel, member National Academy of Engineering
David McAlees, former President Siemens Nuclear Fuels
Harry Harmon, former Hanford tank waste manager
Greg Choppin, Professor of Nuclear Chemistry, Florida State University
Archimedes has also attracted prominent scientists as investors in the Company
-
Ted Geballe, Stanford University, Professor Emeritus in Applied Physics
Daniel Koshland, UC – Berkeley, Professor Emeritus, past Manhattan Project scientist
Ken Fowler, former Associate Director Lawrence Livermore National Labs
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Archimedes Has Created a Global R&D Effort
Key Partnerships Have Helped us Meet Technical Milestones
Demonstration Commercial
Program
Plant
Collaboration / Role in the Archimedes Process
UC San Diego
UC Berkeley
Univ. of Texas
St Petersburg Univ. Russia
Budker Institute Novosibirsk,
Russia
CEA, France
EDF, French Utility
Oak Ridge Nat’l Lab





Physics tests and diagnostics equipment; Start-up electrode



Calcination of HLW and LAW waste; Glass studies; Off-gas
Physics tests and diagnostics equipment
Physics tests and diagnostics equipment; Plunge probe
Torch used to vaporize waste into Filter; Studies on molten NaOH
Electrode/ Light Collector Design and fabrication; Electrode power
supply design and component fabrication
Two visiting scientists/engineers


RF Antenna Modeling; Conceptual Design: Remote Maintenance


Criticality Safety analysis for commercial plant design
Cogema/SGN

Conceptual Design: Off-gas treatment; Waste removal; Systems
design
Nuvotec


Filter plant detailed process flow model
Battelle/PNWD
Westinghouse SMS
Jacobs Engineering
BWXT
Pacific Northwest Division. Hanford process flow; Archimedes
integration and cost savings analysis; chemical engineers
Hanford Teaming Agreement Partner (Plant Design); Conceptual
Design: AFP Design Balance of Plant
Hanford Teaming Agreement Partner (Plant Operator)
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Archimedes Plasma Mass Filter Separates Ions by Mass
•
Filter takes advantage of the “mass gap” in Hanford tank waste between
radioactive and non-radioactive species.
relative amount
Na-23
Al-27
Fe-56
100%
Archimedes
“Filter Function”
Sr-90
Cs-137
TRU
90%
mass
99.9%
radionuclides
50%
59
89
atomic weight (g/mol)
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Filter Subsystems
RF Antennas
(Ionize Waste)
Electrodes
(Rotate Plasma)
Light Collector
Heavy Collector
Sub-Micron Powder Injector
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The Archimedes Two Filter Plant is Small and has Modest
Infrastructure Needs
Archimedes
Filter Plant
Licensing and
Permitting
3.4 acres Land Area
(~6% of WTP Site)
“Valve Pit”
connections with
Tank Farm
Power Grid (average power
need of 38MW, 55MW peak)
Basic Infrastructure
Requirements (water, steam,
sample testing, security, etc)
Product Feed and
Receipt Requirements
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Hanford ORP Solids Dissolution Targets Result in IHLW Reduction
Archimedes Offers an Alternative for Even Greater Reduction
HLW Glass Estimates (MT)1
300,000
200,000
100,000
0
Tank Inventory Estimate
HLW Solids:
HLW Glass*:
84,403 MT
272,000 MT
Water Washing
Caustic Washing
17,553 MT
73,000 MT
10,100 MT
46,100 MT
~50% of
W.W Solids
Archimedes Filter
Plant
Oxidative Leaching
9,858 MT
3 4,676 MT (ORP “revised target”)
Reduction of
~17,000MT HLW
Glass
• Hanford’s baseline targets dissolution of ~90% of the tank HLW oxides to yield an inventory of 9,860
MT solids to be sent to vitrification, producing 34,676 MT of HLW glass and take 22 years to
process.2
• Deployment of a 2-Unit Archimedes Filter Plant could process ~50% of the W.W. Solids
inventory would yield a total reduction of ~17,000MT HLW glass produced by WTP.
– provides WTP operational flexibility as an alternative pre-treatment path for HLW solids
*Notes: (1) HLW glass production assumes ORP’s “relaxed” glass model.
(2) Assumes 6 MTG/day with 70% utilization for HLW Vit and 1.1 MT oxide/day per Archimedes Filter with 70% utilization.
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Integration of Archimedes offers Broad Technical and
Operational Benefits for Hanford and the WTP
• Provides an alternate pretreatment path for HLW solids to HLW vitrification
operations
• Reduced burden on the HLW melter performance and utilization requirements due
to significant reduction of solids inventory and removal of key elements that limit
waste loading in the HLW glass, such as chrome, sulfate and phosphate
• Filter separation process is less vulnerable to waste batch uncertainty and
variability
• Could eliminate need for Oxidative Leaching process
• Net reduction of ILAW glass due to reduction of caustic leaching and sodium added
• Reduces residual environmental impact by directing 99Tc and 129I to IHLW rather
than ILAW
• Reduces burden on HLW interim storage, transportation and repository
requirements
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Archimedes Filter Plant Deployment Analysis
Waste Inventory Based on ORP Refined Target Case, RPP-23412
•
Deployment of 2-Filter Archimedes Filter Plant (AFP) would:
–
–
–
treat selected batches (~46% of water-washed solids mass) over 14 years
reduces overall IHLW glass production by 50%
reduces estimated WTP processing time by 8 years
WW Solids Treatment Path [1]
Archimedes Filter Plant
WW Solids Pretreatment by WTP
IHLW MT Glass Produced [2]
WTP Only
WTP with 2-Filter AFP
0%
46%
100%
54%
34,000
17,000
Processing Years [4]
WTP Operations [3]
Completion [4]
22
14
2037
2029
Notes
[1] Estimated 17,550 MT HLW water washed solids in 590 batches
[2] Assumes DOE "relaxed" glass model
[3] Assumes 6 MTG/day with 70% utilization for HLW Vit and 1.1 MT oxide/day per Archimedes Filter with 70% utilization.
[4] Assumes startup in 2013 plus 2 years commissioning (no production)
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How the Archimedes Filter Works
How the Filter Works
Magnet Coils
Magnetic field
Heavy ions
RF Antenna
Electric field
Electric field
RF Antenna
Light ions
Electrodes
Electrodes
Waste injected
as sub-micron
powder
Side view of the plasma column
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Filter Physics – Ions are Guided by Electric and Magnetic Fields
Axial magnetic field (B) confine light ions (blue)
Radial electric field (E) expels heavy ions (red)
B
E
E
B
side view
end view
Radial force balance on ions of mass m and charge Ze rotating with speed vq:
ZeE  Zevq B
electric
magnetic

mvq2
r
0
centrifugal
Heavy ions are expelled if their mass exceeds the “cutoff mass” mc
ZeB2a 2
mc 
,
8V0
2V0r
E  2 0
a
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Effects of Collisions Simulated with Monte-Carlo Model
•
Design of Archimedes Filter Plant requires a high throughput: 0.26 ion-mol/s.
•
Collisions between ions and other plasma particles can degrade separation.
•
Monte-Carlo computer simulation tracks ion trajectories in Filter E and B fields,
including collisions with background plasma and neutrals.
•
Good separation at high density with reasonable electric and magnetic fields
Light
Elements
Light
Elements
Heavy Elements
Side View
Na yellow
Al blue
Fe green
Cr
cyan
Sr Cs Pu red
End View
Each curve shows the trajectory
of an ion in the plasma
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Archimedes Filter Process
plasma formation
LAW
rotation / separation
collection / removal
IHLW
feed preparation
injection
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Photo of DEMO − the Archimedes DEMOnstration Unit
Vacuum pumps
RF Transmission Lines
Magnetic Field Coils
Electrodes
Vacuum Vessel
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Demo Diagnostics
Bolometer
Plunge Probe
w/4 Point Tip
LIBS-L
Gattling
Gun
(Heavy
Coupons)
IR Inspection
Periscope
LIBS-H
Light Coupon
System
(Both Sides)
Heavy Collector
Boroscope
Light Coupon
and Handler
Light
Collector
Optical Arrays
Microwave
Interferometer
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So How Is It Working So Far?
Filter Demonstration
Overview
• Six steps will separate waste into LAW and HLW streams:
–
Feed preparation: receive water-washed slurry from waste tanks; calcine and
convert to powder for injection into Filter
–
Injection: deliver waste to Filter in a form that plasma can digest
–
Plasma formation: convert injected waste to plasma ions
–
Rotation/Separation: rotate waste plasma to separate heavy ions from light ions
–
Collection: Accumulate distinct light and heavy waste deposits at collectors
–
Removal: Clean collectors to remove heavy and light waste deposits
• This talk will give results for each step to date, and describe the objectives
to demonstrate each step on Hanford surrogates
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Feed Preparation Process Will Convert Water Slurry to
Calcined Powder
Feed preparation
aqueous
slurry
feed receipt
initial sizing / milling
spray drying to < 50 mm
powder
ICP
calcination, submicron
powder production
Filter
HLW
sizing
particle / gas separation
LAW
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Calcination and Conversion of Surrogate to Dry Powder has
been Demonstrated
Spray Dryer System to be tested with Niro Inc.
Plasma Calcination System tested with CEA
•
Niro Inc. has successfully completed feasibility testing with Hanford surrogate
elements, and is ready to perform a pilot study on the full surrogate
•
Plasma calcination from slurry to dry powder has been demonstrated with
Hanford Envelope D surrogate at CEA’s Marcoule facility in France.
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Generation of Sub-Micron Powders from Hanford Surrogate
has been Demonstrated On-Site
• Conversion of waste surrogate
(representative of AZ-101) from
spray-dried dimensions to submicron scale has been
demonstrated on-site
ICP input:
waste surrogate
powder with
typical dimension
~ 20 mm
• Optimization of vapor
condensation conditions will
allow control of conversion
efficiency and powder size
• Calcination efficiency of this
process needs to be
characterized
ICP output:
surrogate powder
with typical
dimension < 1 mm
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Direct Powder Injection System is Installed at the Demo Filter
Powder Injection in Plasma
Injection Nozzle
Evaporation Model
•
A fluidized bed delivery system is currently
installed on the Demo Filter. 0.05 mm powders
have been radially injected into the Filter with
low driving gas flow rates
•
Injection rates up to 2 g/s have been reached
(target is 5 g/s)
•
Modeling of particle trajectories in the Filter
plasma predicts full evaporation of 0.20 mm
alumina particles
Powder Plume
Powder Injection Nozzle
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Waste Throughput is Maximized by Control of Plasma Shape
-3
Electron Density (m )
1.5E+19
5.0E+18
Plasma center
1.0E+19
0.0E+00
0
10
20
30
40
Filter Radius (cm)
•
The RF power deposition profile is controlled by phasing of currents in
each antenna strap
•
Flat density profiles will maximize waste throughput and ionization
efficiency
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Conversion of Submicron Surrogate Powder into Plasma
has been Demonstrated
• Emitted light measurements
from the plasma indicate
successful evaporation and
conversion to plasma ions
• Current work is focused on
maximizing ionization
efficiency and throughput
through injection control
–
The injection region is
controlled by injection nozzle
shape and location
20130 low res heavy
0.7
Ion Light Intensity
• A complex waste surrogate
(75% Al2O3, 15% Fe3O4, 6%
ZrCaO3, 4% BiO2) has been
injected
Ar ii 488
Al ii 390.06
0.6
RF power ramps up
0.5
Argon
Aluminum
0.4
0.3
0.2
0.1
0
10
20
30
40
50
60
Time [sec]
Alumina powder injection starts
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Separation Demonstration Geometry
Heavy Collector
•
Separation experiments were performed with edge injection of AZ-101
surrogate by laser evaporation
–
•
Light Collector
Surrogate
Vapor
Major constituents in AZ-101 target: Si, Al, Fe, Zr, Bi
Spectroscopic measurements (red lines) and surface coupon measurements
(red arrows) are used to study injected surrogates
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Plasma Profiles are Ideal for Separation
80
Plasma center
6.E+18
4.E+18
2.E+18
0.E+00
60
40
20
Plasma center
Electric Potential (V)
-3
Electron Density (m )
8.E+18
Measured by Probe
Applied at Electrodes
0
0
10
20
Radius (cm)
30
40
0
10
20
30
Radius (cm)
•
Source control in sodium plasma maintains filled profiles in rotating plasma
•
A parabolic electric potential applied to the light collectors causes the
plasma to rotate
•
Probe measurements in the plasma show that the applied potential
penetrates along the magnetic field
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Doppler Measurements Confirm Rigid Body Rotation at
of Fe and Bi Vaporized with Laser from PNNL Target
E x Rotation
B Velocity
Plasma center
ExB
100 V
900 G
•
Doppler spectroscopy measures plasma rotation speed in the Heavy
Collector region for Bi and Fe from injected Hanford AZ-101 Surrogate
•
Rotation scales with applied electric field
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Applying Cutoff Electric Field Sends Heavy Elements to the
Heavy Collector
Material Accumulated at Light Collector
Material Accumulated at Heavy Collector
2.5
1.5
1
1.5
1
0.5
0.5
0
0
Si
Without Cutoff
With Cutoff
2
Total Mass (g)
Total Mass (g)
2
2.5
Without Cutoff
With Cutoff
Fe
Ca
Element
Bi
Si
Ca
Fe
Bi
Element
• Battelle AZ-101 tank waste surrogate injected into sodium background
plasma by laser evaporation
• 100 V bias at 900 Gauss (cutoff mass = 134 AMU) used to separate
bismuth (208 AMU) from lighter elements
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Surface Measurements at Light and Heavy Collectors Show
Cutoff of Bismuth at Expected Voltage
0.8
1
Light Collector
Sodium Fraction
Bismuth Fraction
1
0.6
0.4
0.2
Heavy Collector
0
-20
Light Collector
0.8
0.6
0.4
0.2
Heavy Collector
0
0
20
40
60
Electrode Voltage [V]
80
-20
0
20
40
60
Electrode Voltage [V]
80
Bi Vc=63.6V
Below cut-off
99% Bismuth -> light collector
Above cut-off
85% Bismuth -> heavy collector
15% Bismuth -> light collector
No cut-off
99% of collected sodium
is on the light collector
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Filter Function Matches Numerical Simulation for Edge
Injection
100%
Light Collector Fraction, %
Coupons: ICP-AES
Coupons: XRF
80%
Si
60%
Simulation: Monte Carlo
Fe
40%
Zr
Cutoff mass
150 AMU
20%
Bi
0%
0
50
100
150
200
250
Atomic Mass (AMU)
•
ICP and XRF diagnostics give similar results
•
Edge injection of vapor leads to scrape-off effect
•
Monte Carlo simulations using measured plasma parameters are in
quantitative agreement with the data
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Full Throughput Demonstration Filter Simulation Shows Good
Cutoff of Heavy Elements
Na Al
Light Collector Fraction, %
100
Cr
80
60
Fe
40
20
Sr
Cs
DF=30
Bi
DF=900
DF=400
0
0
50
100
150
200
250
Atomic Mass, AMU
Cutoff = 84 AMU
•
Monte Carlo simulation at full Filter density, magnetic field, and electric
field show high decontamination factors for heavy elements
•
Injection for this simulation is at radii less than 20 cm
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Higher Density and Magnetic Field of AFP Improves Filter
Function
Na Al
Ca
Light Collector Fraction, %
100
80
Cr
Fe
60
Tc DF
40
>100
20
Sr DF
Cs DF
Bi DF
Pu DF
= 50
>1000
>1000 >1000
0
0
50
100
150
200
250
300
Atomic Mass, AMU
Cutoff = 80 AMU
•
The AFP Filter will operate at slightly higher density and magnetic field, and
has a different collector geometry
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Hanford Test Program
High Throughput Separation Optimization
•
The tests will confirm that the Filter can:
–
Separate Hanford waste at high throughput rates and achieve separation
decontamination factors matching those specified below
Radionuclides
Percent of
HLW
Batches
Percent of
WTP Contract Minimum
Allowance for Required
On-site Disp. AFP DF
AFP
Target
DF
TRU
95%
Class C
Requirement
Sr-90
100%
20%
50
Cs-137
100%
4%
60 >>100
76 >>100
~100
Hanford
Test
Program
Target DF
>>100
~30 - 60
>>100
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Light Ion Collection
Conical Electrode/light Collector
Design
• Water-cooled copper rings can
withstand full throughput heat loads
• Collector surface intercepts all ion
orbits
• Insulating stand-offs and feed-throughs
are protected from the plasma heat
• Collection rate
~ 5 mm per hour at full demo throughput
• Access ports available for coupon
surface sampling of collected deposits
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Heavy Ion Collector
Paddlewheel Design
• Collector surface intercepts heavy
ion orbits
• Tilted paddles minimize plasma
refuelling by sputtered heavy
particles
• Open geometry allows neutral gas
pumping
• Collection rates
–
–
–
less than 0.15 mm/hr at full Demo
throughput
Up to 1.5 mm/hr on the plasma
edge due to radial electric currents
Extended operation without
cleaning is possible
heavy ion orbit
• Cooling allows steady state
operation at full throughput
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Demo Status
Summary
• Filter separation physics demonstrated
– Plasma rotates at required velocity for separation
– Expected decontamination factors are measured for heavy elements
– Separation scales with electrode voltage and magnetic field
• Basic technology solutions demonstrated
–
–
–
–
–
Surrogate preparation: calcination and conversion to powder
Injection: delivery of surrogate into the plasma
RF heating: conversion of injected surrogate into plasma
Electrodes: plasma rotation and separation
Collectors: collection and recovery of separated surrogate
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DEMO Parameters are Near Target for Full Throughput
Separation Tests
Parameter
Engineering Maximum
Value Achieved
Hanford Test Program
Goal
Plasma Radius (m)
0.4
0.4
Plasma Length (m)
3.9
3.9
1600
1500
RF Frequency (MHz)
4
4
RF Power (MW)
3
3
2.0
2.0
0.04
0.1
300
500
7
13
600
Steady State
Magnetic Field (Gauss)
Plasma Density (1e19 m-3)
Throughput (ion-mol/s)
Electrode Voltage (Volts)
Ion Temperature (eV)
Discharge Duration (s)
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Plasma Based Separations: 21st Century Technology
Solution for Nuclear Waste and a Proliferation
Resistant Commercial Fuel Cycle
Background
• Currently the National Waste Policy Act (NWPA) of 1982, as amended,
limits Yucca Mt. to 70,000 MT of spent nuclear fuel
–
7,000 MT is reserved for DOE defense waste
–
Remaining 63,000 MT is adequate for spent fuel from existing fleet of reactors if all
plants are shut down by 2010
–
120,000 MT is required if all operating reactors are granted 20 yr extensions
–
Geologic exploration indicates Yucca Mt could expand to 119,000 MT with NWPA
amendment
• The DOE must report to Congress on the need for a second repository in
2010
• Future repository strategy is likely to incorporate ‘actinide burning’ in
advanced reactors to reduce storage capacity demands
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Expected U.S. Repository Needs in 2100 (AFCI Source)
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Reprocessing Technologies for Spent Nuclear Fuel
• Reprocessing to recycle Pu in MOX reactor fuel (PUREX)
– Similar to French La Hague Plant in technology, capacity & cost
 700 acre, 6000 employees, 1700 MT/year capacity
 FP & actinide waste immobilized in borosilicate glass
 After MOX recycle, Pu is separated and stored for future reactors
• Reprocessing to extract uranium (UREX) and chemically separate FP from
actinides (UREX+)
– Requires U extraction and FP separation, but no Pu extraction
 Uranium recycle or disposal as low-level waste (LLW)
 Cs & Sr stored in surface repository for ~300 years, then disposal as LLW
 Actinides immobilized in glass with disposal in Yucca Mt or stored for future use
as nuclear fuel
• Hybrid reprocessing with UREX and Archimedes Filter
– UREX uranium extraction followed by Filter separation of FP & actinides
 U extraction (UREX) is the same, but FP & Pu/actinide separation by physical
process
 Achieves same objectives as chemical reprocessing plant with much less byproduct radioactive waste
 Offers cost and schedule advantages
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Comparison of UREX, UREX+ and UREX-AFP Process Streams
Spent Fuel
100 wt%
45GWd/MT, 10y cooling
Storage
0.6 wt%
Cutting
Dissolution
Clarification
Xe, I, Kr
Insoluble stream
Fission
Product
s 1.58
wt%
72.02 wt%
U
Actinide
s 0.29
wt%
AFP
UREX
Fission
products
Cladding (Zircaloy, Steel)
insoluble stream
if not treated
Tc
0.07 wt%
CCD-PEG
Cs, Sr
0.32 wt%
NPEX
Pu,
Np, U
.96 wt%
3.25 wt%
Actinides
1.32 wt%
22.74 wt%
TRUEX
Am, Cm,
Rare Earths
Am, Cm
CYANEX 301
0.07 wt%
Fission products
1.35 wt%
UREX-AFP
UREX+
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Archimedes Filter Function Spent for Commercial Fuel
Group Separation
12
100
% of isotope separated by heavy collector
10
6
kg/ spent fuel ton
%
8
4
2
Np
2
Pu 37
24
Am 2
2
Cm 4 3
24
5
0
Br
8
Se 1
8
Rb 2
87
Y
89
Sr
90
Zr
9
M 6
o
Ru 98
1
Rh 04
1
Pd 03
10
Ag 8
1
Cd 09
1
Sb 16
12
Sn 3
12
Tr 6
1
Cs 30
13
Ba 7
1
La 38
13
Ce 9
1
Pr 42
14
Nd 1
1
Pm 50
14
Sm 7
1
Eu 5 4
1
G 54
d
15
8
0
isotopes
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UREX-AFP Mission and High Level Requirements
• Mission:
– The hybrid UREX pretreatment and Archimedes Filter Plant mass separation
process will enable expansion of Yucca Mt capacity to ~250,000 MT of spent
nuclear fuel.
• Requirements:
– Process 2000 MT of spent nuclear fuel per year
– Separation of FP from Pu/actinides sufficient to achieve desired repository
capacity
– Provide least environmental impact of all alternative technologies
– Plant startup consistent with first shipments to Yucca Mt
– Provide option to extract Pu if desired
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UREX-AFP Simplified Flow Sheet (45GWd/MT, 10y Cooling)
Cladding
294 kg
Feed
1300 kg
Gas 8.5 kg
Cutting
Dissolution
Extraction
UREX
Gas
Treatment
Insoluble
Stream
24 kg
Raffinate
Stream
35 kg
Uranium
Re-extraction
Tc
1
kg
Uranium
Stripping
Uranium
936 kg
Gas x kg
Pre-treatment
ARCHIMEDES
Filter
Actinide
s
17 kg
Fission
Products
(42– x)
kg
Surface Repository
AFP
Storage or recycle
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Summary of Process Stream Contents
Elements
U (kg/MT)
Pu (kg/MT)
Minor Actinides
(kg/Mt)
Fission Produc
ts minus Tc
Metal cladding
(kg/MT)
Tc (kg/MT)
Total (kg/MT)
%
Spent fuel
input
Removed
by UREX
Raffinate
stream
Insoluble
stream
Processed by
ARCHIMEDES
filter
940.75
936.05
0.94
3.76
4.70
11.00
0.00
10.89
0.04
10.93
1.56
0.00
1.55
0.01
1.55
45.34
0.00
21.75
14.61
36.36
300.00
0.00
0.00
6.00
6.00
1.03
0.98
0.05
0.00
0.05
1299.68
937.03
35.18
24.42
59.60
100.00
72.10
2.71
1.88
4.59
(45GWd/MT,
10 y cooling)
NB : 8.51 kg of gas and 294 kg or metal cladding are removed after rod cutting and dissolution
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Implementation Comparison of Alternative Technologies
• Reprocessing with MOX fuel recycle
– High cost and schedule
– LWR plants may opt to not use MOX fuel
– Does not expand repository capacity
• Reprocessing with UREX+ radio-chemical plant
– Highest cost and schedule
– Environmental impact greater than UREX-AFP
– Significantly expands repository capacity
• Reprocessing with hybrid UREX and AFP plant
– Lowest cost and shortest schedule
– Same repository benefits as UREX+ radio-chemical plant
– Least environmental impact
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BACKUP SLIDES
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