Verification & Validation of HighOrder ShortCharacteristicsBased Deterministic Transport Methodology on Unstructured Grids
Abstract
The research team has developed a practical, highorder, discreteordinates, short characteristics neutron transport code for threedimensional configurations represented on unstructured tetrahedral grids that can be used for realistic reactor physics applications at both the assembly and core levels. This project will perform a comprehensive verification and validation of this new computational tool against both a continuousenergy Monte Carlo simulation (e.g. MCNP) and experimentally measured data, an essential prerequisite for its deployment in reactor core modeling. Verification is divided into three phases. The team will first conduct spatial mesh and expansion order refinement studies to monitor convergence of the numerical solution to reference solutions. This is quantified by convergence rates that are based on integral error norms computed from the cellbycell difference between the code’s numerical solution and its reference counterpart. The latter is either analytic or very fine mesh numerical solutions from independent computational tools. For the second phase, the team will create a suite of codeindependent benchmark configurations to enable testing the theoretical order of accuracy of any particular discretization of the discrete ordinates approximation of the transport equation. For each tested case (i.e. mesh and spatial approximation order), researchers will execute the code and compare the resulting numericalmore »
 Authors:

 North Carolina State Univ., Raleigh, NC (United States)
 Publication Date:
 Research Org.:
 North Carolina State Univ., Raleigh, NC (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Sponsoring Org.:
 USDOE, Nuclear Energy University Programs (NEUP)
 OSTI Identifier:
 1111549
 Report Number(s):
 DOE/NEUP09798
TRN: US1600168
 DOE Contract Number:
 AC0705ID14517
 Resource Type:
 Technical Report
 Country of Publication:
 United States
 Language:
 English
 Subject:
 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; NUMERICAL SOLUTION; VALIDATION; NEUTRON TRANSPORT THEORY; COMPARATIVE EVALUATIONS; ATR REACTOR; DISCRETE ORDINATE METHOD; MONTE CARLO METHOD; COMPUTERIZED SIMULATION; EXACT SOLUTIONS; ERRORS; VERIFICATION; THREEDIMENSIONAL LATTICES; REACTOR CORES; CONVERGENCE; THREEDIMENSIONAL CALCULATIONS; ACCURACY; COORDINATES; BENCHMARKS; DISTRIBUTION; SERIES EXPANSION; ZERO POWER REACTORS
Citation Formats
Azmy, Yousry, and Wang, Yaqi. Verification & Validation of HighOrder ShortCharacteristicsBased Deterministic Transport Methodology on Unstructured Grids. United States: N. p., 2013.
Web. doi:10.2172/1111549.
Azmy, Yousry, & Wang, Yaqi. Verification & Validation of HighOrder ShortCharacteristicsBased Deterministic Transport Methodology on Unstructured Grids. United States. https://doi.org/10.2172/1111549
Azmy, Yousry, and Wang, Yaqi. 2013.
"Verification & Validation of HighOrder ShortCharacteristicsBased Deterministic Transport Methodology on Unstructured Grids". United States. https://doi.org/10.2172/1111549. https://www.osti.gov/servlets/purl/1111549.
@article{osti_1111549,
title = {Verification & Validation of HighOrder ShortCharacteristicsBased Deterministic Transport Methodology on Unstructured Grids},
author = {Azmy, Yousry and Wang, Yaqi},
abstractNote = {The research team has developed a practical, highorder, discreteordinates, short characteristics neutron transport code for threedimensional configurations represented on unstructured tetrahedral grids that can be used for realistic reactor physics applications at both the assembly and core levels. This project will perform a comprehensive verification and validation of this new computational tool against both a continuousenergy Monte Carlo simulation (e.g. MCNP) and experimentally measured data, an essential prerequisite for its deployment in reactor core modeling. Verification is divided into three phases. The team will first conduct spatial mesh and expansion order refinement studies to monitor convergence of the numerical solution to reference solutions. This is quantified by convergence rates that are based on integral error norms computed from the cellbycell difference between the code’s numerical solution and its reference counterpart. The latter is either analytic or very fine mesh numerical solutions from independent computational tools. For the second phase, the team will create a suite of codeindependent benchmark configurations to enable testing the theoretical order of accuracy of any particular discretization of the discrete ordinates approximation of the transport equation. For each tested case (i.e. mesh and spatial approximation order), researchers will execute the code and compare the resulting numerical solution to the exact solution on a per cell basis to determine the distribution of the numerical error. The final activity comprises a comparison to continuousenergy Monte Carlo solutions for zeropower critical configuration measurements at Idaho National Laboratory’s Advanced Test Reactor (ATR). Results of this comparison will allow the investigators to distinguish between modeling errors and the abovelisted discretization errors introduced by the deterministic method, and to separate the sources of uncertainty.},
doi = {10.2172/1111549},
url = {https://www.osti.gov/biblio/1111549},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2013},
month = {12}
}