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NRC Source Term Research Outstanding Issues and Future Directions. Farouk Eltawila, Director Division of Risk Assessment & Special Projects Office Nuclear Regulatory Research U.S. Nuclear Regulatory Commission. Accident Source Terms in the US regulatory process.

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Nrc source term research outstanding issues and future directions

NRC Source Term ResearchOutstanding Issues and Future Directions

Farouk Eltawila, Director

Division of Risk Assessment & Special Projects

Office Nuclear Regulatory Research

U.S. Nuclear Regulatory Commission


Accident source terms in the us regulatory process
Accident Source Terms in the US regulatory process

  • Releases of fission products to the containment:

    • Defense in depth

    • Regulatory evaluation of engineered safety features (ESFs)

  • Releases of fission products to the environment:

    • Consequences of reactor accidents

    • Accident management and emergency response


History
HISTORY

  • Most current reactors licensed to the TID-14844 Source Term to the containment

    • Derived from heating irradiated fuel in a furnace

    • Releases

      • 100 % Noble gases

      • 50% iodine as a gas (half of this deposits)

      • 1% of all other radionuclides as particles

      • Instantly available in containment


History continued
HISTORY continued

  • The accident at TMI changed perceptions

    • Severe accident possible

    • Source term different

  • Nuclear Regulatory Commission asked for a better, more realistic source term

  • NRC Research initiated a major initiative to develop a mechanistic source term

    • Tie to risk important accidents – not DBAs

    • Eventually about $500 million spent


Nrc severe accident source term research
NRC Severe Accident Source Term Research

  • Massive undertaking to understand

    • Accident progression within RCS

      • In-pile tests (PBF, ACRR, DF, FLHT, etc.)

    • Exvessel phenomena

      • Melt-concrete interactions

      • Steam explosions

      • Hydrogen combustion

    • Fission product chemistry

      • Deposition in RCS

      • Aerosol physics

    • Containment integrity


Culminated in
Culminated in

  • Alternate Source Term for licensing

    • NUREG-1465

  • NUREG-1150 Level III risk analysis of five representative US nuclear power plants

    • 3 PWRs

    • 2 BWRs

  • Integrated, systems-level, accident analysis computer code to preserve understanding

    • Initially, Source Term Code Package

    • Later MELCOR


Alternate source term
Alternate Source Term

  • Timing based on four accident phases in BWRs and PWRs separately:

    • Gap release (clad ballooning and rupture)

    • In-vessel release (core degradation)

    • Ex-vessel release (melt/concrete etc.)

    • Late in-vessel release (revaporization)

  • Release magnitudes based on mechanistic analysis of important accident sequences for many plants

    • 8 chemical groups of fission products

    • Most aerosol

    • 5% of released iodine gaseous



Alternate source term1
Alternate Source Term

  • Very popular with licensees

    • Timing features allow safer

      • Diesel start times

      • Isolation valve closure times

      • Etc.


A research climax but not a conclusion
A Research Climax but not a Conclusion

  • NUREG-1150 made clear many uncertainties remained

    • Estimated release fractions to environment could vary by factors of 10 to 1000

    • Source terms adequate for regulatory needs of the time

    • As use of PRA and more advanced reactors developed, better source term understanding needed


Examples of Radionuclide Release Uncertainties

from NUREG-1150

RSS = Reactor Safety Study predictions circa 1975


Collaborative experimental research
Collaborative Experimental Research

  • PHEBUS-FP: realistic FP chemistry in RCS and containment

  • ARTIST: mitigation of risk dominant accident for PWRs

  • RASPLAV/MASCA: feasibility of in-vessel retention and FP release in late stage degradation

  • MCCI: attenuation of ex-vessel source term with water

PreTest

Post Test


Comparison of Alternative MELCOR Models

of Cesium Release to Data from PHEBUS test

Validation of the Alternate Source Term for reactor licensing


Issues for current lwrs
Issues for Current LWRs

  • Iodine behavior in containment

    • Steady-state gaseous iodine in containment atmosphere

    • Interactions with paint

    • Utility of containment sump buffering

    • PHEBUS-EPICUR and AECL tests

  • Chemical form of cesium released to containment

    • Cesium molybdate versus cesium hydroxide

    • PHEBUS-CHIP tests


Issues for advanced lwr certification
Issues for Advanced LWR Certification

  • AP-1000

    • Diffusiophoretic deposition of aerosol on containment walls

    • Effects of aerosol shape factors

  • ESBWR

    • Iodine behavior in the drywell and passive safety systems


Future
FUTURE

Fuel Kernel

  • Next Generation Nuclear Plant

    • Source terms from gas-cooled graphite reactors

    • Triso fuel

    • Completed phenomena identification and importance ranking exercises

graphite

Silicon

carbide

Coated particle fuel for gas reactor


Future1
FUTURE

  • Global Nuclear Energy Partnership

    • Source terms from sodium-cooled reactors

    • Defining regulatory approach


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