nrc source term research outstanding issues and future directions
Download
Skip this Video
Download Presentation
NRC Source Term Research Outstanding Issues and Future Directions

Loading in 2 Seconds...

play fullscreen
1 / 18

NRC Source Term Research Outstanding Issues and Future Directions - PowerPoint PPT Presentation


  • 81 Views
  • Uploaded on

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.

loader
I am the owner, or an agent authorized to act on behalf of the owner, of the copyrighted work described.
capcha
Download Presentation

PowerPoint Slideshow about 'NRC Source Term Research Outstanding Issues and Future Directions' - ishana


An Image/Link below is provided (as is) to download presentation

Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author.While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server.


- - - - - - - - - - - - - - - - - - - - - - - - - - E N D - - - - - - - - - - - - - - - - - - - - - - - - - -
Presentation Transcript
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
slide12
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

slide14
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
ad