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Title: Bayesian Monte Carlo Evaluation of Imperfect (n, 233U) Data and Model

Conference ·
 [1];  [1];  [1];  [1];  [2];  [3]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
  2. OECD Nuclear Energy Agency, Paris (France)
  3. University of Tennessee, Knoxville, TN (United States)

Conventional nuclear data evaluation methods using generalized linear least squares make the following assumptions: prior and posterior probability distribution functions (PDFs) of all model parameters and data are normal (Gaussian); the linear approximation is sufficiently accurate to minimize the cost function (even for nonlinear models); the model (e.g., of neutron cross section) and experimental data (including covariance data) are without defect and prior PDFs of parameters and measured data are known perfectly. Neglect of covariance between model parameters and measured data in conventional evaluations contributes to imperfections. These assumptions are inherent to the generalized linear least squares minimization method commonly used for resolved resonance region neutron cross section evaluations but are often not justified due to the presence of non-normal PDFs, nonlinear models (e.g., R-matrix formalism), and inherent imperfections in data and models (e.g., imperfect covariance data). Here, these assumptions are removed in a mathematical framework of Bayes’ theorem, which is implemented using the Metropolis-Hastings Monte Carlo method. Most importantly, new parameters are introduced to parameterize discrepancies between the theoretical model and measured data to quantify judgement about discrepancies or imperfections in a reproducible manner. An evaluation of 233U in the eV region using the ENDF-B/VIII.0 library and transmission data (Guber et al.) is presented, and posterior parameters are compared to those obtained by conventional evaluation methods. This example illustrates the effects of removing the most harmful assumption: that of model-data perfection.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); OECD Nuclear Energy Agency, Paris (France); Univ. of Tennessee, Knoxville, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1994781
Report Number(s):
183495
Resource Relation:
Conference: 15. International Conference on Nuclear Data for Science and Technology (ND2022), Held Virtually, 21-29 Jul 2023; Related Information: https://indico.frib.msu.edu/event/52/overview
Country of Publication:
United States
Language:
English

References (7)

Differential Cross Sections and the Impact of Model Defects in Nuclear Data Evaluation journal January 2016
Understanding the Metropolis-Hastings Algorithm journal November 1995
Estimation via Markov chain Monte Carlo conference January 2002
Stationarity and Convergence of the Metropolis-Hastings Algorithm: Insights into Theoretical Aspects journal February 2019
Multilevel Formula for the Fission Process journal August 1958
R-Matrix Theory of Nuclear Reactions journal April 1958
High-Resolution Transmission Measurements of 233 U Using a Cooled Sample at the Temperature T = 11 K journal October 2001