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FRAPCON Statistical Package. FRAPCON/FRAPTRAN Users Group Meeting September 7, 2012 Paul Clifford Division of Safety Systems Office of Nuclear Reactor Regulation. Statistical Package.

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frapcon statistical package

FRAPCON Statistical Package

FRAPCON/FRAPTRAN Users Group Meeting

September 7, 2012

Paul Clifford

Division of Safety Systems

Office of Nuclear Reactor Regulation

statistical package
Statistical Package
  • FRAPCON-3.4 designed to provide best-estimate predictions. NRC needed ability to perform independent fuel rod design calculations.
  • FRAPCON statistical package performs the following tasks:
    • randomly samples among specified distributions of manufacturing tolerances, modeling uncertainties, and rod power uncertainties,
    • creates multiple FRAPCON input decks,
    • executes each of these unique cases, and
    • compiles the results (e.g., plots, 95/95 UTL, data files).
  • Statistical package also allows introduction of a power ramp to existing rod power history.
    • User specifies ramp magnitude (KW/ft), time duration, and burnup time step.
manufacturing tolerances
Manufacturing Tolerances
  • Manufacturing tolerances may be defined as a variety of distributions including uniform and normal.
modeling uncertainties
Modeling Uncertainties
  • FRAPCON calibration modeling uncertainties defined in NUREG/CR-7022, Volume 2.
usage
Usage
  • NRC using FRAPCON statistical package to perform independent fuel rod design calculations.
    • End-of-life rod internal pressure.
    • LOCA initialization (stored energy).
    • AOO overpower cladding strain.
    • AOO overpower fuel power-to-melt.
  • FRAPCON confirmatory calculations may support review of a variety of licensing applications.
    • New fuel rod designs.
    • Fuel vendor transitions.
    • Power uprates.
    • Condition reporting (e.g., fuel thermal conductivity degradation).
    • Review of new fuel performance models/methods.
pwr 16x16 uo2 rod 1
PWR 16x16 – UO2 Rod 1

Calculated end-of-life rod internal pressure (500 cases):

Nominal = 1676 psia

95/95 with sampled TOL = 1847 psia

95/95 with sampled TOL + FGR = 1873 psia

95/95 with sampled TOL + FGR + POW = 2015 psia

pwr 16x16 uo2 rod 2
PWR 16x16 – UO2 Rod 2

Calculated end-of-life rod internal pressure (500 cases):

Nominal = 1809 psia

95/95 with sampled TOL = 1977 psia

95/95 with sampled TOL + FGR = 2088 psia

95/95 with sampled TOL + FGR + POW = 2332 psia

pwr 14x14 ugdo2 rod
PWR 14x14 – UGdO2 Rod

Calculated end-of-life rod internal pressure (500 cases):

Nominal = 1319 psia

95/95 with sampled TOL = 1463 psia

95/95 with sampled TOL + FGR = 1785 psia

95/95 with sampled TOL + FGR + POW = 1820 psia

conclusions
Conclusions
  • FRAPCON statistical package provides a robust tool for performing independent fuel rod design calculations.
  • During the past 12 months, NRC has completed confirmatory calculations to support the following licensing actions:
    • Calvert Cliffs Units 1 &2 fuel transition (CE 14x14).
    • Turkey Point Units 3 & 4 extended power uprate (W 15x15).
    • St. Lucie Unit 1 extended power uprate (CE 14x14).
    • St. Lucie Unit 2 extended power uprate (CE 16x16).
  • NRC will continue to utilize statistical package to support licensing actions.
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