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Dive into the research topics where Dimitrios C. Kontogeorgakos is active.

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Featured researches published by Dimitrios C. Kontogeorgakos.


Archive | 2013

Initial Neutronics Analyses for HEU to LEU Fuel Conversion of the Transient Reactor Test Facility (TREAT) at the Idaho National Laboratory

Dimitrios C. Kontogeorgakos; K. Derstine; Arthur E. Wright; T. Bauer; J. Stevens

The purpose of the TREAT reactor is to generate large transient neutron pulses in test samples without over-heating the core to simulate fuel assembly accident conditions. The power transients in the present HEU core are inherently self-limiting such that the core prevents itself from overheating even in the event of a reactivity insertion accident. The objective of this study was to support the assessment of the feasibility of the TREAT core conversion based on the present reactor performance metrics and the technical specifications of the HEU core. The LEU fuel assembly studied had the same overall design, materials (UO2 particles finely dispersed in graphite) and impurities content as the HEU fuel assembly. The Monte Carlo N–Particle code (MCNP) and the point kinetics code TREKIN were used in the analyses.


Archive | 2015

Overview and Current Status of Analyses of Potential LEU Design Concepts for TREAT

Heather M. Connaway; Dimitrios C. Kontogeorgakos; Dionissios D. Papadias; Arthur E. Wright

Neutronic and thermal-hydraulic analyses have been performed to evaluate the performance of different low-enriched uranium (LEU) fuel design concepts for the conversion of the Transient Reactor Test Facility (TREAT) from its current high-enriched uranium (HEU) fuel. TREAT is an experimental reactor developed to generate high neutron flux transients for the testing of nuclear fuels. The goal of this work was to identify an LEU design which can maintain the performance of the existing HEU core while continuing to operate safely. A wide variety of design options were considered, with a focus on minimizing peak fuel temperatures and optimizing the power coupling between the TREAT core and test samples. Designs were also evaluated to ensure that they provide sufficient reactivity and shutdown margin for each control rod bank. Analyses were performed using the core loading and experiment configuration of historic M8 Power Calibration experiments (M8CAL). The Monte Carlo code MCNP was utilized for steady-state analyses, and transient calculations were performed with the point kinetics code TREKIN. Thermal analyses were performed with the COMSOL multi-physics code. Using the results of this study, a new LEU Baseline design concept is being established, which will be evaluated in detail in a future report.


Archive | 2014

Neutronics Analyses of the Minimum Original HEU TREAT Core

Dimitrios C. Kontogeorgakos; Heather M. Connaway; G. Yesilyurt; Arthur E. Wright

This work was performed to support the feasibility study on the potential conversion of the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory from the use of high-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by the GTRI Reactor Conversion staff at the Argonne National Laboratory (ANL). The objective of this study was to validate the MCNP model of the TREAT reactor with the well-documented measurements which were taken during the start-up and early operation of TREAT. Furthermore, the effect of carbon graphitization was also addressed. The graphitization level was assumed to be 100% (ANL/GTRI/TM-13/4). For this purpose, a set of experiments was chosen to validate the TREAT MCNP model, involving the approach to criticality procedure, in-core neutron flux measurements with foils, and isothermal temperature coefficient and temperature distribution measurements. The results of this study extended the knowledge base for the TREAT MCNP calculations and established the credibility of the MCNP model to be used in the core conversion feasibility analysis.


Archive | 2016

Analysis of the TREAT LEU Conceptual Design

Heather M. Connaway; Dimitrios C. Kontogeorgakos; D. D. Papadias; A. J. Brunett; K. Mo; P. S. Strons; T. Fei; Arthur E. Wright


Archive | 2014

TREAT Transient Analysis Benchmarking for the HEU Core

Dimitrios C. Kontogeorgakos; Heather M. Connaway; Arthur E. Wright


Journal of Nuclear Materials | 2017

Effect of reactor radiation on the thermal conductivity of TREAT fuel

Kun Mo; Yinbin Miao; Dimitrios C. Kontogeorgakos; Heather M. Connaway; Arthur E. Wright; Abdellatif M. Yacout


Archive | 2016

Effect of Ractor Radiation on the Thermal Conductivity of Graphite-based Dispersion Fuel

Kun Mo; Yinbin Miao; Arthur E. Wright; Dimitrios C. Kontogeorgakos; Heather M. Connaway; Abdellatif M. Yacout


Archive | 2015

Neutronics and Transient Calculations for the Conversion of the Transient Reactor Rest Facility (TREAT)

Dimitrios C. Kontogeorgakos; Heather M. Connaway; Dionissios D. Papadias; Arthur E. Wright


Archive | 2015

Temperature Dependence of Test Fuel Power Density and Core Energy during Transient Reactor Test Facility (TREAT) Irradiation Experiments

Dimitrios C. Kontogeorgakos; Heather M. Connaway; Arthur E. Wright


Archive | 2015

Temperature Limited Transient Calculations for the Transient Reactor Test Facility (TREAT) Using MCNP and the Point Kinetics Code TREKIN

Dimitrios C. Kontogeorgakos; Heather M. Connaway; Keith L. Derstine; Arthur E. Wright; Sean Morrell

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Arthur E. Wright

Argonne National Laboratory

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Kun Mo

Argonne National Laboratory

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Sean Morrell

Idaho National Laboratory

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Yinbin Miao

Argonne National Laboratory

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A. J. Brunett

Argonne National Laboratory

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D. D. Papadias

Argonne National Laboratory

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G. Yesilyurt

Argonne National Laboratory

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