Enhanced geometric capabilities for the transient analysis code TReX and its application to simulating TREAT experiments
Abstract
Here, advances in computational architecture have prompted a resurgence in the simulation of reactor transients from first principles. Most codes are unable to simulate transient events with complex models, and require numerous approximations. The code TReX (TransientReactor eXperiment simulator), an extensive update to TDKENO, has been developed as a transient analysis tool with few geometric limitations and minimal theoretical approximations. TReX achieves this by employing the Improved QuasiStatic (IQS) method to solve the time dependent Boltzmann transport equation with explicit representation of delayed neutrons. The primary change in TReX relative to TDKENO is the incorporation of a modified version of the Monte Carlo code KENOVI to calculate the flux shape and model the geometry of a problem. Using KENOVI to model systems allows exact representation of the geometry. The changes to TReX are verified by comparison of solutions to computational benchmark problems found with a previous version of TDKENO that made use of KENO V.a, and several other codes with timedependent capabilities. In addition, a threedimensional model of the Transient Reactor Test Facility (TREAT) core at the Idaho National Laboratory (INL) is constructed with KENOVI, and used to validate T ReX. TReX produces results that agree with benchmark problems, andmore »
 Authors:

 Nuclear Engineering Program, Gainesville, FL (United States)
 Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Publication Date:
 Research Org.:
 Idaho National Lab. (INL), Idaho Falls, ID (United States)
 Sponsoring Org.:
 USDOE Office of Nuclear Energy (NE)
 OSTI Identifier:
 1478408
 Alternate Identifier(s):
 OSTI ID: 1548683
 Report Number(s):
 INL/JOU1741078Rev000
Journal ID: ISSN 01491970
 Grant/Contract Number:
 AC0705ID14517; 156392
 Resource Type:
 Accepted Manuscript
 Journal Name:
 Progress in Nuclear Energy
 Additional Journal Information:
 Journal Volume: 105; Journal Issue: C; Journal ID: ISSN 01491970
 Publisher:
 Elsevier
 Country of Publication:
 United States
 Language:
 English
 Subject:
 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 97 MATHEMATICS AND COMPUTING; TREAT; Transient; TReX; KENO; IQS; Neutron; IQS method; Neutron transport; Time dependent
Citation Formats
Mausolff, Zander, DeHart, Mark, and Goluoglu, Sedat. Enhanced geometric capabilities for the transient analysis code TReX and its application to simulating TREAT experiments. United States: N. p., 2018.
Web. doi:10.1016/j.pnucene.2018.01.013.
Mausolff, Zander, DeHart, Mark, & Goluoglu, Sedat. Enhanced geometric capabilities for the transient analysis code TReX and its application to simulating TREAT experiments. United States. doi:10.1016/j.pnucene.2018.01.013.
Mausolff, Zander, DeHart, Mark, and Goluoglu, Sedat. Tue .
"Enhanced geometric capabilities for the transient analysis code TReX and its application to simulating TREAT experiments". United States. doi:10.1016/j.pnucene.2018.01.013. https://www.osti.gov/servlets/purl/1478408.
@article{osti_1478408,
title = {Enhanced geometric capabilities for the transient analysis code TReX and its application to simulating TREAT experiments},
author = {Mausolff, Zander and DeHart, Mark and Goluoglu, Sedat},
abstractNote = {Here, advances in computational architecture have prompted a resurgence in the simulation of reactor transients from first principles. Most codes are unable to simulate transient events with complex models, and require numerous approximations. The code TReX (TransientReactor eXperiment simulator), an extensive update to TDKENO, has been developed as a transient analysis tool with few geometric limitations and minimal theoretical approximations. TReX achieves this by employing the Improved QuasiStatic (IQS) method to solve the time dependent Boltzmann transport equation with explicit representation of delayed neutrons. The primary change in TReX relative to TDKENO is the incorporation of a modified version of the Monte Carlo code KENOVI to calculate the flux shape and model the geometry of a problem. Using KENOVI to model systems allows exact representation of the geometry. The changes to TReX are verified by comparison of solutions to computational benchmark problems found with a previous version of TDKENO that made use of KENO V.a, and several other codes with timedependent capabilities. In addition, a threedimensional model of the Transient Reactor Test Facility (TREAT) core at the Idaho National Laboratory (INL) is constructed with KENOVI, and used to validate T ReX. TReX produces results that agree with benchmark problems, and are in better agreement with TREAT experimental data than TDKENO.},
doi = {10.1016/j.pnucene.2018.01.013},
journal = {Progress in Nuclear Energy},
number = C,
volume = 105,
place = {United States},
year = {2018},
month = {2}
}
Web of Science