Frapcon statistical package
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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

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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.


Statistical package cont

Statistical Package (cont.)


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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