Molten Salt Reactor Development 2017 Molten Salt Reactor Workshop - - PowerPoint PPT Presentation

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Molten Salt Reactor Development 2017 Molten Salt Reactor Workshop - - PowerPoint PPT Presentation

Molten Salt Reactor Development 2017 Molten Salt Reactor Workshop Oak Ridge Tennessee Lou Qualls, Ph.D. National Technical Director for MSRs quallsal@ornl.gov Reactor and Nuclear Systems Division Oak Ridge National Laboratory October 3, 2017


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ORNL is managed by UT-Battelle for the US Department of Energy

Molten Salt Reactor Development

Lou Qualls, Ph.D. National Technical Director for MSRs quallsal@ornl.gov Reactor and Nuclear Systems Division Oak Ridge National Laboratory October 3, 2017

2017 Molten Salt Reactor Workshop Oak Ridge Tennessee

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2 MSR Vendors Forum – 5/1/17 – ORNL

Why Nuclear?

  • Energy density
  • Low-carbon electricity
  • National energy security
  • Diverse energy portfolio

– PB-FHR fuel pebbles

  • Four 3.0-cm diameter pebbles can provide electricity for a year for an average U.S.

household

  • 8.1 tons of anthracite coal, or 17 tons of lignite coal are needed to produce the same

amount of electricity using a coal power plant.

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3 MSR Vendors Forum – 5/1/17 – ORNL

Why Advanced Reactors?

– Better safety posture – Lower costs – Reduced accident consequences – Expanded siting options – Better resource utilization – Ability to close the fuel cycle – Reduced waste products

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4 MSR Vendors Forum – 5/1/17 – ORNL

Why MSRs?

  • High-temperature, low-pressure systems with chemically inert fluids

– Lower-cost components – Dry heat rejection capability

  • Large temperature margins to boiling

– Passive safety response – Fewer safety critical systems

  • Large baseload or small modular deployment
  • Continual salt and fission product processing possible

– Reduced emergency planning zone (?) – Ability to use UNF – Ability to help close the fuel cycle and reduce waste to repositories

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5 MSR Vendors Forum – 5/1/17 – ORNL

MSR Passive Safety: The Freeze Plug

  • In the event of TOTAL loss of power, the

freeze plug melts and the core salt drains into a passively cooled configuration where nuclear criticality is impossible.

  • The reactor is equipped with a

“freeze plug”—an open line where a frozen plug of salt is blocking the flow.

  • The plug is kept frozen by an

external cooling fan.

Freeze Plug Drain Tank

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6 MSR Vendors Forum – 5/1/17 – ORNL

MSRs are a broad class of advanced reactors

  • MSRs are revolutionary for the implementation of nuclear power
  • MSRs can revitalize the U.S. nuclear energy sector
  • MSRs are near-term innovations
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7 MSR Vendors Forum – 5/1/17 – ORNL

How do you get into a market?

Sell a product or provide a service

  • Either

– Produce cost-competitive electricity or industrial heat

  • Lower capital cost
  • Lower O&M costs
  • Or

– Play a positive role in closing the fuel cycle

  • Or

– Uniquely meet the needs of a niche market

  • High quality heat
  • “expensive” power for special applications
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8 MSR Vendors Forum – 5/1/17 – ORNL

What do we need to get MSRs to market?

  • Materials, salts, and an understanding of their behavior
  • Enabling technology
  • Design rules and standards
  • Reactor designs and mod-sim methods to effectively evaluate their performance
  • A convincing story of reactor safety and source term management
  • Understanding and agreements about ultimate waste forms
  • A business case for the concept
  • A well-defined path for licensing of the first reactors
  • A follow-on path for licensing commercial reactors
  • Interested investors and a supportive government
  • Supply chains and supporting infrastructure
  • Initial fuel core loadings
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9 MSR Vendors Forum – 5/1/17 – ORNL

New Chemistry and Reactor Modeling Challenges

  • Understand reactor performance and behavior

– Develop and integrate dynamic salt chemistry models with neutronic and thermal hydraulic analyses for reactor performance evaluation all the way through severe accident transients

  • Understand source term behavior

– Develop constituent lifecycle data and models to account for source term behavior

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10 MSR Vendors Forum – 5/1/17 – ORNL

DOE MSR FY18 Priorities

  • Materials and salt combinations and their interactions
  • Salt chemistry data, database, and chemistry models
  • Enabling technology
  • Concept evaluation
  • Modeling and simulation
  • Licensing and safeguards
  • Salt processing, reuse, and waste forms
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11 MSR Vendors Forum – 5/1/17 – ORNL

Which Molten Salt Reactors are we interested in?

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12 MSR Vendors Forum – 5/1/17 – ORNL

Which Molten Salt Reactors are we interested in?

  • All of them
  • “if you’re interested in it, we’re interested in it”
  • The market needs diversity
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13 MSR Vendors Forum – 5/1/17 – ORNL

Which Molten Salt Reactors are we interested in?

  • All of them
  • “if you’re interested in it, we’re interested in it”
  • The market needs diversity
  • Our job is to facilitate an environment in which new reactors can be

developed

  • We are not designing a DOE reactor or picking winning designs
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14 MSR Vendors Forum – 5/1/17 – ORNL

Each concept requires acceptable materials and salts

ΔT

Hot Leg Cr++ Cold Leg

dissolution

Cr

saturation deposition

2UF4(d) + Cr = 2UF3(d) + CrF2(d) Oxidant + Cr = Reductant + CrF2(d)

AK RIDGE NATIONAL LABORATORY

. S. DEPARTMENT OF ENERGY

Initial ! impurity-driven! corrosion! Persistent! Cyclic Corrosion Mechanism!

(slope proportional to U-content)!

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15 MSR Vendors Forum – 5/1/17 – ORNL

Salt

  • peration

Salt changes corrosion Salt monitoring Salt processing Salt corrective actions Salt preparation Post reactor processing

Each concept needs a “Cradle-to-Grave” plan

waste Reuse Existing Inventories

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16 MSR Vendors Forum – 5/1/17 – ORNL

We’ve got to do something soon

(M. Herald and M. Adkisson)

5000 10000 15000 20000 25000 30000 35000 12/27/14 6/18/20 12/9/25 6/1/31 11/21/36 5/14/42 11/4/47 4/26/53 10/17/58 4/8/64

Approximate nuclear capacity in the southeast U.S. (MW)

Date

Projection showing the loss of nuclear capacity in the southeast U.S

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17 MSR Vendors Forum – 5/1/17 – ORNL

DOE is taking a focused, near-term development approach to reactor development and deployment

  • Science
  • Technology
  • Development
  • Demonstration
  • First reactors
  • Next reactors

~10 years ~15 - 20 years

  • Salts, materials and their interactions
  • Components, processes, systems
  • Reactor concepts
  • Engineering scale testing

Licensing and Safeguards

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18 MSR Vendors Forum – 5/1/17 – ORNL

Notional Timeline to MSR Deployment

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19 MSR Vendors Forum – 5/1/17 – ORNL

Molten Salt Reactor Experiment

  • Timeline
  • Salt loaded into tanks - Oct. 24, 1964
  • Salt first circulated through core - Jan. 12, 1965
  • First criticality (U235) - June 1, 1965
  • First operation in megawatt range - Jan. 24, 1966
  • Full power reached - May 23, 1966
  • Nuclear operation with U235 concluded
  • Strip uranium from fuel salt - Aug. 23-29, 1968
  • First criticality with U233 Oct. 2, 1968
  • Full power reached with U233 Jan. 28, 1969
  • Nuclear operation concluded - Dec. 2, 1969
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20 MSR Vendors Forum – 5/1/17 – ORNL

Questions? Thank you