Bias and uncertainty assessment of pressurized water reactor fuel isotopics using SCALE

Ryan N. Bratton, Kostadin N. Ivanov, Matthew A. Jessee, William A. Wieselquist

Research output: Contribution to conferencePaperpeer-review

3 Scopus citations

Abstract

The purpose of this study is to investigate bias and uncertainty in fuel isotopic calculations for a well-defined radiochemical assay benchmark with Sampler, the new sampling-based uncertainty quantification tool in the SCALE code system. Isotopic predictions are compared to measurements of fuel rod MKP109 of assembly D047 from the Calvert Cliffs Unit 1 core at three axial locations, representing a range of discharged fuel burnups. A methodology is developed which quantifies the significance of input parameter uncertainties and modeling decisions on isotopic prediction by comparing to isotopic measurement uncertainties. The SCALE Sampler model of the D047 assembly incorporates input parameter uncertainties for key input data such as multigroup cross sections, decay constants, fission product yields, the cladding thickness, and the power history for fuel rod MKP109. The effects of each set of input parameter uncertainty on the uncertainty of isotopic predictions have been quantified. In this work, isotopic prediction biases are identified and an investigation into their sources is proposed; namely, biases have been identified for certain plutonium, europium, and gadolinium isotopes for all three axial locations. Moreover, isotopic prediction uncertainty resulting from only nuclear data is found to be greatest for Eu-154, Gd-154, and Gd-160.

Original languageEnglish
StatePublished - 2014
Event2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, Japan
Duration: Sep 28 2014Oct 3 2014

Conference

Conference2014 International Conference on Physics of Reactors, PHYSOR 2014
Country/TerritoryJapan
CityKyoto
Period09/28/1410/3/14

Funding

This work has been partially funded by both Oak Ridge National Laboratory (ORNL) and the Nuclear Regulatory Commission. This research was performed during the Nuclear Engineering Science Laboratory Synthesis (NESLS) program of ORNL. This manuscript has been authored by the Oak Ridge National Laboratory, managed by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The US Government retains and the publisher, by accepting the article for publication, acknowledges that the US Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US Government purposes. This manuscript has been authored by the Oak Ridge National Laboratory, managed by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the US Department of Energy. The US Government retains and the publisher, by accepting the article for publication, acknowledges that the US Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US Government purposes. This work has been partially funded by both Oak Ridge National Laboratory (ORNL) and the Nuclear Regulatory Commission. This research was performed during the Nuclear Engineering Science Laboratory Synthesis (NESLS) program of ORNL.

Keywords

  • Bias
  • Calvert Cliffs
  • SCALE
  • Sampler
  • Spent fuel isotopics
  • Uncertainty

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