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Title: Enhanced geometric capabilities for the transient analysis code T-ReX 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 T-ReX (Transient-Reactor eXperiment simulator), an extensive update to TDKENO, has been developed as a transient analysis tool with few geometric limitations and minimal theoretical approximations. T-ReX achieves this by employing the Improved Quasi-Static (IQS) method to solve the time dependent Boltzmann transport equation with explicit representation of delayed neutrons. The primary change in T-ReX relative to TDKENO is the incorporation of a modified version of the Monte Carlo code KENO-VI to calculate the flux shape and model the geometry of a problem. Using KENO-VI to model systems allows exact representation of the geometry. The changes to T-ReX 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 time-dependent capabilities. In addition, a three-dimensional model of the Transient Reactor Test Facility (TREAT) core at the Idaho National Laboratory (INL) is constructed with KENO-VI, and used to validate T ReX. T-ReX produces results that agree with benchmark problems, andmore » are in better agreement with TREAT experimental data than TDKENO.« less

Authors:
ORCiD logo [1]; ORCiD logo [2];  [1]
  1. Nuclear Engineering Program, Gainesville, FL (United States)
  2. 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/JOU-17-41078-Rev000
Journal ID: ISSN 0149-1970
Grant/Contract Number:  
AC07-05ID14517; 156392
Resource Type:
Accepted Manuscript
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 105; Journal Issue: C; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 97 MATHEMATICS AND COMPUTING; TREAT; Transient; T-ReX; 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 T-ReX 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 T-ReX 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 T-ReX 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 T-ReX 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 T-ReX (Transient-Reactor eXperiment simulator), an extensive update to TDKENO, has been developed as a transient analysis tool with few geometric limitations and minimal theoretical approximations. T-ReX achieves this by employing the Improved Quasi-Static (IQS) method to solve the time dependent Boltzmann transport equation with explicit representation of delayed neutrons. The primary change in T-ReX relative to TDKENO is the incorporation of a modified version of the Monte Carlo code KENO-VI to calculate the flux shape and model the geometry of a problem. Using KENO-VI to model systems allows exact representation of the geometry. The changes to T-ReX 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 time-dependent capabilities. In addition, a three-dimensional model of the Transient Reactor Test Facility (TREAT) core at the Idaho National Laboratory (INL) is constructed with KENO-VI, and used to validate T ReX. T-ReX 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}
}

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