@inproceedings{21a38c1227264fb186896e1c66c19a76,
title = "A fission matrix based validation protocol for computed power distributions in the advanced test reactor",
abstract = "The Idaho National Laboratory (INL) has been engaged in a significant multiyear effort to modernize the computational reactor physics tools and validation procedures used to support operations of the Advanced Test Reactor (ATR) and its companion critical facility (ATRC). Several new protocols for validation of computed neutron flux distributions and spectra as well as for validation of computed fission power distributions, based on new experiments and well-recognized least-squares statistical analysis techniques, have been under development. In the case of power distributions, estimates of the a priori ATR-specific fuel element-to-element fission power correlation and covariance matrices are required for validation analysis. A practical method for generating these matrices using the element-to-element fission matrix is presented, along with a high-order scheme for estimating the underlying fission matrix itself. The proposed methodology is illustrated using the MCNP5 neutron transport code for the required neutronics calculations. The general approach is readily adaptable for implementation using any multidimensional stochastic or deterministic transport code that offers the required level of spatial, angular, and energy resolution in the computed solution for the neutron flux and fission source.",
keywords = "Covariance, Fission Matrix, Least-Squares, Neutron Transport, Validation",
author = "Nielsen, \{Joseph W.\} and Nigg, \{David W.\} and LaPorta, \{Anthony W.\}",
note = "Funding Information: This work was supported by the U.S. Department of Energy (DOE), via the ATR Life Extension Program under BattelleEnergy Alliance , LLC Contract no. DE-AC07-05ID14517 with DOE. The authors also wish to gratefully acknowledge several useful discussions with Dr. John G. Williams, University of Arizona, on the general subject of covariance matrices and their role in this type of analysis.; International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 ; Conference date: 05-05-2013 Through 09-05-2013",
year = "2013",
language = "English",
isbn = "9781627486439",
series = "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013",
pages = "1577--1593",
booktitle = "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013",
}