30.04.2014 Views

John Rawls - US Nuclear Waste Technical Review Board

John Rawls - US Nuclear Waste Technical Review Board

John Rawls - US Nuclear Waste Technical Review Board

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

Implications for <strong>Waste</strong> Handling of the<br />

Energy Multiplier Module<br />

by<br />

<strong>John</strong> <strong>Rawls</strong><br />

June 29, 2010<br />

132-10/rs<br />

1


Changing the Game for <strong>Nuclear</strong> Energy<br />

Key National Issues<br />

1. Economics<br />

2. Used <strong>Nuclear</strong> Fuel<br />

3. Non-Proliferation<br />

4. Energy Security<br />

5. Human Dimension<br />

EM 2 Goals<br />

– To reduce capital investment and<br />

power cost by 30% compared to ALWRs<br />

– To consume & reduce used nuclear fuel<br />

inventory, i.e. minimize need for long-term<br />

repositories<br />

– To reduce need for uranium enrichment;<br />

eliminate conventional fuel reprocessing<br />

– To advance electrification through siteflexibility<br />

& process heat applications;<br />

to reduce foreign energy imports<br />

– To attract eager young minds to a<br />

challenging new enterprise<br />

132-10/rs<br />

2


EM 2 is a Fast Gas-Cooled Reactor in which Fuel is<br />

Made and Burned in situ<br />

Schematic EM 2 core<br />

control drum<br />

fertile<br />

starter<br />

reflector<br />

Argonne National Laboratory<br />

predicted longer core life and<br />

lower excess reactivity<br />

k-effective<br />

1.15<br />

1.10<br />

1.05<br />

1.00<br />

0.95<br />

0.90<br />

0.85<br />

Basics of the breed and<br />

burn in situ approach<br />

• A starter region containing fissile<br />

material provides initial criticality<br />

• The burn spreads to the fertile region,<br />

where it is sustained by newly bred fuel<br />

• The geometrical arrangement has low<br />

excess reactivity for decades, improving<br />

fuel utilization and simplifying control<br />

EM 2 core reactivity<br />

0 10 20 30 40<br />

Time (Yr)<br />

132-10/rs<br />

3


Reactor Concept<br />

Point design features<br />

• 500 MWt, He cooled at 850 o C outlet<br />

suitable for process heat applications<br />

• 240 MW e at ~48% net efficiency (~45%<br />

with dry cooling), at power cost<br />

comparable to natural gas at $7/Mbtu<br />

Grade<br />

Power<br />

Conversion<br />

Module<br />

• Burns used LWR fuel w/o reprocessing<br />

(also DU, natural U, WPu, Th admixture)<br />

• 30 + -yr core w/o refueling or reshuffling;<br />

EOL core can be recycled with 30-60%<br />

fission product removal<br />

• Passively safe, underground sited<br />

• Modules factory manufactured &<br />

shipped by commercial trucks<br />

18 m<br />

5 m<br />

Reactor<br />

132-10/rs<br />

4


Core Composition and Arrangement<br />

Fuel Elements<br />

(typ. of 21 per<br />

layer)<br />

Reactor<br />

Return Flow<br />

Annulus<br />

Core Barrel<br />

Reactor<br />

Vessel Wall<br />

5.0 m (15.6 ft)<br />

B4C Layer<br />

(100 mm<br />

thickness)<br />

Graphite<br />

Reflector Layer<br />

(500 mm<br />

thickness)<br />

BeO Layer (250 mm<br />

minimum thickness)<br />

Material irradiation data is encouraging about the life of SiC structure<br />

Fuel Element<br />

17,136 units<br />

SiC-SiC<br />

clad<br />

porous UC<br />

plate<br />

SiC-SiC Assembly<br />

Frame<br />

Positions plates<br />

for cooling & FP<br />

control<br />

Fuel Assembly<br />

357 units<br />

• Handling unit<br />

• Stackable<br />

• Transfers fission gas<br />

5.19kg<br />

Fission gas<br />

movement<br />

Fission gas<br />

movement<br />

257kg<br />

132-10/rs<br />

5


Used <strong>Nuclear</strong> Fuel/DU and Partial Closing of<br />

the Fuel Cycle<br />

132-10/rs<br />

6


Energy Security: Fuel Utilization 1 Improves with<br />

Number of Cycles<br />

50%<br />

45%<br />

Fuel Utilization<br />

40%<br />

35%<br />

30%<br />

25%<br />

20%<br />

EM 2 First Cycle:<br />

2X LWR Utilization<br />

SNF waste<br />

U.S. SNF inventory: 61,000 t<br />

15%<br />

2<br />

U.S. DOE NE Goal: 10%<br />

10%<br />

5%<br />

0%<br />

LWR 0.5%<br />

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20<br />

Number of EM 2 Cycles<br />

1<br />

Percent of mined heavy metal that is fissioned 2<br />

U.S. Department of Energy, <strong>Nuclear</strong> Energy<br />

DU waste<br />

U.S. DU inventory: 700,000 t<br />

Energy in U.S. SNF & DU<br />

inventory is 5 x world’s<br />

proven oil reserves<br />

132-10/rs<br />

7


Quantity of <strong>Waste</strong> Produced<br />

<strong>Waste</strong> (tonnes)<br />

12000<br />

10000<br />

8000<br />

6000<br />

4000<br />

2000<br />

0<br />

-2000<br />

LWR<br />

EM 2<br />

0 100 200 300 400<br />

<strong>Waste</strong> vs years of operation for a<br />

continuously operating1.2 GWe plant<br />

Impact on repository sizing<br />

(stated on a per unit energy<br />

supplied basis)<br />

• Higher burnup and higher<br />

efficiency mean lower end of<br />

life fuel mass & volume<br />

• These amounts are reduced<br />

further (linearly) by the<br />

number of times fuel is reused<br />

• These figures of merit are<br />

further improved if spent LWR<br />

fuel is used as fuel<br />

Total waste in 400 years: LWR 12,000t, EM 2 < 400t<br />

132-10/rs<br />

8


Implications for <strong>Nuclear</strong> <strong>Waste</strong><br />

1.E+07<br />

EM 2 Decay After 30-year Burnup<br />

1.E+05<br />

EM 2 Core Decay Heat After 30-year Burnup<br />

Actinides<br />

Fission Products<br />

1.E+04<br />

Decay Activity (Curies)<br />

1.E+06<br />

1.E+05<br />

1.E+04<br />

Decay Energy (Watts)<br />

1.E+03<br />

1.E+02<br />

1.E+01<br />

Actinides<br />

Fission Products<br />

1.E+00<br />

1.E+03<br />

1.E-01<br />

1 10 100 1000 10000<br />

1 10 100 1000 10000<br />

Decay Time (years)<br />

Decay Time (years)<br />

__________________________________________________________________________________________<br />

FP radiological data<br />

• FP makeup quite similar to that of LWRs except<br />

that Cs is removed from the core during the burn<br />

• After 300 yrs, primary FPs are 99 Tc & 151 Sm, two<br />

weak beta emitters; FP heat load is few W/core<br />

Actinide radiological data<br />

• If restricted to one burn cycle, actinide content<br />

per unit energy produced is similar to that of LWRs<br />

and is reduced linearly with the number of cycles<br />

• Long core residence postpones repository need<br />

132-10/rs<br />

9


Non-Proliferation<br />

Dry cask storage<br />

1. Reduces fuel handling and eliminates long-term<br />

storage of spent fuel containing significant Pu.<br />

Uranium enrichment<br />

2. Eliminates need for conventional reprocessing<br />

(heavy metal chemical separation).<br />

3. Both discharged and refabricated EM 2 fuel<br />

meets self-protection requirements for 20 yrs.<br />

Geological repositories<br />

4. Below-grade reactor core is inaccessible without<br />

special remote handling equipment.<br />

5. Low excess reactivity- core cannot be easily<br />

reconfigured for material insertion/extraction<br />

132-10/rs<br />

10<br />

10<br />

185-09/RWS/rs


Comparative Power Generation Costs<br />

30% cost reduction is a result<br />

of the following attributes<br />

• Less materials<br />

• Factory labor<br />

• Shorter construction time<br />

• Smaller facility footprint<br />

• Higher efficiency<br />

• Decades of life —<br />

no refueling/no shuffling<br />

• Simple control<br />

• Bankablility of fuel<br />

ALWR, coal and natural gas data source: MIT 2009 Cost Update; EM 2 model estimate.<br />

All power generation costs evaluated for a 30-yr levelization period<br />

132-10/rs<br />

11


DOE-NE Comprehensive EM 2 Peer <strong>Review</strong><br />

- Core physics and depletion<br />

- Core thermal hydraulics<br />

- Fuels<br />

- Fission product transport<br />

- Used fuel management<br />

- Structural materials<br />

- Balance of plant<br />

- Safety<br />

- Non-proliferation<br />

- Cost/economics<br />

Key findings:<br />

• Most significant risks are associated with 30-yr core in fast neutron fluence, including<br />

fuel thermal-chemical performance and dimensional stability, SiC clad integrity, and<br />

fission product transport<br />

• Report affirms the reactor physics design and that EM 2 supports all five DOE-NE goals<br />

132-10/rs<br />

12<br />

185-09/RWS/rs


GA’s Internally-Funded Program Addresses<br />

Fuel and Power Conversion<br />

CY2010 GA-Funded Work<br />

UC Lab<br />

- Bench-scale UC fab facility<br />

- Bench-scale SiC fab facility<br />

- Fuel fab process optimization<br />

- Physics methods upgrade<br />

- Reactivity control design<br />

- EM 2 fuel metrology lab<br />

- High-speed generator<br />

- High-voltage inverter<br />

- Reactor concept optimization<br />

- Power conversion design<br />

- Selected accident analyses<br />

- FP transport component fab<br />

SiC Composite Lab<br />

SiC coater<br />

High-speed<br />

Gas Turbine<br />

132-10/rs<br />

13<br />

13<br />

185-09/RWS/rs


Summary<br />

• Significant capital & power cost reduction<br />

• Reduces (and potentially consumes) the used<br />

nuclear fuel inventory, thereby easing repository<br />

requirements and possibly delaying their need<br />

• Reduces long-term need for enrichment;<br />

eliminates need for conventional reprocessing<br />

• Formidable technical challenges are attracting<br />

eager young minds to a new nuclear enterprise<br />

with a long-term future<br />

132-10/rs<br />

14


Backup Slides<br />

132-10/rs<br />

15


EST Also Offers Promise for Used <strong>Nuclear</strong> Fuel<br />

Fission Products<br />

Heavy Metals<br />

• Uses mass gap between actinides and lanthanides<br />

• Separation of trivalent actinides and lanthanides considered to be the<br />

most difficult current reprocessing steps<br />

– Necessary for both repository management and recycled fuel<br />

• Filter throughput 30X less than wastes much smaller size plant<br />

132-10/rs<br />

16


EST Technology Proof of Principle has Occurred<br />

• Physically separates based on mass/charge using electromagnetic fields<br />

• Advantages for nuclear wastes<br />

– Relatively indifferent to<br />

waste complexity<br />

– Excellent separation efficiency<br />

– Single step process<br />

– Reduced waste streams<br />

– Significant net cost savings<br />

and risk reduction<br />

• Advantages for used nuclear fuel processing<br />

– Separates fission products<br />

– Not capable of TRU separation by element or isotopes<br />

– Supportive of new reprocessing-free closed fuel cycle options<br />

132-10/rs<br />

17


Technology Needs & Research Challenges<br />

• Efficient and effective separation of fission products<br />

from reactor discharge<br />

• Understanding properties of materials under high<br />

neutron fluences and high temperatures<br />

• Behavior of fuel and fission products over decades<br />

• Defining and establishing manufacturing base to<br />

realize the cost-effective fabrication of modular<br />

reactors like EM 2<br />

132-10/rs<br />

18


EM 2 is More Proliferation-Resistant than<br />

Alternative Reactor Concepts<br />

Portion of<br />

Fuel Cycle<br />

Attribute of<br />

Fuel Cycle<br />

Light Water<br />

Reactor<br />

Traditional<br />

Fast Reactor<br />

EM 2<br />

Front end Need for enrichment? Yes<br />

Gen 1: yes<br />

Gen 2: no<br />

Gen 1: yes<br />

Gen 2: no<br />

Operations<br />

Fuel residence time<br />

Sealed vessel?<br />

< 5 yr<br />

No<br />

< 5 yr<br />

No<br />

> 30 yr<br />

Yes<br />

Back end Planned reuse of fuel None<br />

Yes, with Pu<br />

separation<br />

Yes, without<br />

Pu separation<br />

Proliferation vulnerability legend<br />

LOW MODERATE HIGH<br />

132-10/rs<br />

19<br />

185-09/RWS/rs

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!