UNCERTAINTY PROPAGATION FOR LWR BURNUP BENCHMARK USING SAMPLING BASED CODE SCALE/SAMPLER

Authors

  • Daniel Campolina Department of Nuclear Reactors, Czech Technical University in Prague, Prague, Czech Republic Nuclear Technology Development Center, Belo Horizonte, Brazil
  • Jan Frybort Department of Nuclear Reactors, Czech Technical University in Prague, Prague, Czech Republic

DOI:

https://doi.org/10.14311/APP.2018.14.0008

Keywords:

random sampling, uncertainty, nuclear fuel burnup, OECD UAM LWR

Abstract

Sampling based method is adopted in many fields of engineering and it is currently used to propagate uncertainties from physical parameters and from nuclear data, to integral indicators of nuclear systems. The total uncertainty associated with a model simulation is of major importance for safety analysis and to guide vendors about acceptable tolerance limits for nuclear installations parts. This work presents some calculations to propagate uncertainties for a nuclear reactor fuel element modeled in SCALE/TRITON, using the sampling tool SCALE/SAMPLER. Results showed that that the influence of input uncertainties on kinf is more pronounced in the fresh core other than the depleted core and the contribution from studied manufacturing uncertainties is smaller than the contribution of nuclear data uncertainties.

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Published

2018-05-17

Issue

Vol. 14 (2018): ŠIMÁNĚ 2017

Section

Articles

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