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Title: Adaptive Reweighted Variance Estimation for Monte Carlo Eigenvalue Simulations

Journal Article · · Nuclear Science and Engineering
 [1]; ORCiD logo [2]
  1. Texas A & M Univ. at Corpus Christi, TX (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Monte Carlo (MC) simulation is used to solve the eigenvalue form of the Boltzmann transport equation to estimate various parameters such as fuel pin flux distributions that are crucial for the safe and efficient operation of nuclear systems (e.g., a nuclear reactor). Monte Carlo eigenvalue simulation uses a sample mean over many stationary cycles (iterations) to estimate various parameters important to nuclear systems. A variance estimate of the sample mean is often used for calculating the confidence intervals. However, MC eigenvalue simulation variance estimators that ignore the intercycle correlation underestimate the true variance of the estimated quantity. This paper presents novel data-adaptive approaches based on a simple autoregressive (AR) model and sigmoid functions to improve MC variance estimation. The standard MC sample-based variance estimator (or naïve estimator) and the spectral density–based MC variance estimator are enhanced by adding data-adaptive components that reduce their bias and improve performance. By investigating the frequency pattern of the AR(1) (order 1) model, two adaptive spectral estimators and one adaptive naïve estimator are proposed. The proposed estimators manifest superior performance when applied to three test problems compared to the standard spectral density–based estimator previously introduced by the authors. In conclusion, these new estimators are straightforward, as they use online algorithms and do not require storage of tallies from all active cycles.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1607052
Journal Information:
Nuclear Science and Engineering, Vol. 194, Issue 3; ISSN 0029-5639
Publisher:
American Nuclear Society - Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (14)

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Underestimation of statistical uncertainty of local tallies in Monte Carlo eigenvalue calculation for simple and LWR lattice geometries journal September 2018
Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations journal June 2016
Batch estimation of statistical errors in the Monte Carlo calculation of local powers journal November 2011
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Time Series Analysis of Monte Carlo Fission Sources–II: Confidence Interval Estimation journal June 2006
Universal Methodology for Statistical Error and Convergence of Correlated Monte Carlo Tallies journal February 2019
A power spectrum approach to tally convergence in Monte Carlo criticality calculation journal August 2017
Sensor validation for power plants using adaptive backpropagation neural network journal April 1990

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