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Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor

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Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor University of Tennessee, Knoxville TRACE: Tennessee Research and Creative Exchange Doctoral Dissertations Graduate School 8-2011 Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor David Chandler [email protected] Follow this and additional works at: https://trace.tennessee.edu/utk_graddiss Part of the Nuclear Engineering Commons Recommended Citation Chandler, David, "Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor. " PhD diss., University of Tennessee, 2011. https://trace.tennessee.edu/utk_graddiss/1066 This Dissertation is brought to you for free and open access by the Graduate School at TRACE: Tennessee Research and Creative Exchange. It has been accepted for inclusion in Doctoral Dissertations by an authorized administrator of TRACE: Tennessee Research and Creative Exchange. For more information, please contact [email protected]. To the Graduate Council: I am submitting herewith a dissertation written by David Chandler entitled "Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor." I have examined the final electronic copy of this dissertation for form and content and recommend that it be accepted in partial fulfillment of the equirr ements for the degree of Doctor of Philosophy, with a major in Nuclear Engineering. G. Ivan Maldonado, Major Professor We have read this dissertation and recommend its acceptance: David H. Cook, Arthur E. Ruggles, Lawrence H. Heilbronn, Rao V. Arimilli Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official studentecor r ds.) To the Graduate Council: I am submitting herewith a dissertation written by David Chandler entitled ―Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor.‖ I have examined the final electronic copy of this dissertation for form and content and recommend that it be accepted in partial fulfillment of the requirements for the degree of Doctor of Philosophy, with a major in Nuclear Engineering. G. Ivan Maldonado, Major Professor We have read this dissertation and recommend its acceptance: David H. Cook Arthur E. Ruggles Lawrence H. Heilbronn Rao V. Arimilli James D. Freels (Courtesy Member) Accepted for the Council: Carolyn R. Hodges Vice Provost and Dean of the Graduate School (Original signatures are on file with official student records.) Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor A Dissertation Presented for the Doctor of Philosophy Degree The University of Tennessee, Knoxville David Chandler August 2011 Copyright © 2011 by David Chandler All rights reserved ii DEDICATION I would like to dedicate this dissertation to my amazing family who has always provided me love, support, and encouragement. I would like to thank my mother, Sheila Chandler, and my sister, Louise Pence, who have always believed in me and had the right words to say during all the stressful times. I would like to thank my girlfriend, Lindsay Sondles, who packed up and moved with me to Tennessee and has been patient and supportive through my years of research. Finally, and most importantly, I would like to dedicate this work to my father, Len Chandler, who always believed in me, encouraged me, and taught me great work ethics. iii ACKNOWLEDGEMENTS This dissertation was made possible by a research contract between the University of Tennessee Nuclear Engineering Department and the Research Reactors Division of the Oak Ridge National Laboratory, which is managed by UT-Battelle for the United States Department of Energy. First and foremost, I would like to express my sincere appreciation to my advising professor, Dr. G. Ivan Maldonado, and my technical mentor, Mr. R. Trent Primm III, for their time, contributions, and guidance in my studies. I would like to thank Dr. Maldonado for pursuing and encouraging me to enroll in graduate school and then continuing to support and advise me. I would like to thank Mr. Primm for providing me with excellent opportunities at one of the top research facilities in the world and always making time to assist me in my studies. I would like to thank the members of my dissertation committee: Dr. James D. Freels, Dr. David H. Cook, Dr. Arthur E. Ruggles, Dr. Rao V. Arimilli, and Dr. Lawrence H. Heilbronn; for their support and assistance during my research and dissertation work. I also want to express my sincere gratitude to Dr. Germina Ilas (ORNL), Dr. Wim Haeck (IRSN in France), and the COMSOL technical support staff who have helped provide me with the computational tools and information needed to perform much of my research. I would also like to thank Mr. Randy W. Hobbs, Mr. Larry D. Proctor, Mr. Ron A. Crone, Dr. Kevin A. Smith, and the rest of the Research Reactors Division for their support and encouragement. Most importantly I would like to thank my family who has always encouraged me and been there for me. The most influential people in my life are my parents, Len and Sheila Chandler, who have believed in me and supported me in all of my life decisions. I would like to thank my sister, Louise Pence, for always believing in me and being there as both a friend and sister. I would also like to send a special thank you to my girlfriend, Lindsay Sondles, who started this journey with me and has supported and believed in me over the years. iv ABSTRACT The computational ability to accurately predict the dynamic behavior of a nuclear reactor core in response to reactivity-induced perturbations is an important subject in the field of reactor physics. Space- time and point kinetics methodologies were developed for the purpose of studying the transient-induced behavior of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor’s (HFIR) compact core. The space-time simulations employed the three-group neutron diffusion equations, which were solved via the COMSOL partial differential equation coefficient application mode. The point kinetics equations were solved with the PARET code and the COMSOL ordinary differential equation application mode. The basic nuclear data were generated by the NEWT and MCNP5 codes and transients initiated by control cylinder and hydraulic tube rabbit ejections were studied. The space-time models developed in this research only consider the neutronics aspect of reactor kinetics, and therefore, do not include fluid flow, heat transfer, or reactivity feedback. The research presented in this dissertation is the first step towards creating a comprehensive multiphysics methodology for studying the dynamic behavior of the HFIR core during reactivity-induced perturbations. The results of this study show that point kinetics is adequate for small perturbations in which the power distribution is assumed to be time-independent, but space-time methods must be utilized to determine localized effects. En route to developing the kinetics methodologies, validation studies and methodology updates were performed to verify the exercise of major neutronic analysis tools at the HFIR. A complex MCNP5 model of HFIR was validated against critical experiment power distribution and effective multiplication factor data. The ALEPH and VESTA depletion tools were validated against post-irradiation uranium isotopic mass spectrographic data for three unique full power cycles. A TRITON model was developed and used to calculate the buildup and reactivity worth of helium-3 in the beryllium reflector, determine whether discharged beryllium reflectors are at transuranic waste limits for disposal purposes, determine whether discharged beryllium reflectors can be reclassified from hazard category 1 waste to category 2 or v 3 for transportation and storage purposes, and to calculate the curium target rod nuclide inventory following irradiation in the flux trap. vi TABLE of CONTENTS DEDICATION .......................................................................................................................................................... III ACKNOWLEDGEMENTS ..................................................................................................................................... IV ABSTRACT ................................................................................................................................................................ V LIST OF FIGURES .................................................................................................................................................. XI LIST OF TABLES ................................................................................................................................................... XV 1 INTRODUCTION .............................................................................................................................................. 1 1.1 ORGANIZATION OF DISSERTATION ........................................................................................................... 1 1.2 MOTIVATION AND GOAL .......................................................................................................................... 3 1.3 LITERATURE REVIEW ............................................................................................................................... 8 1.3.1 HFIR Physics Calculations ............................................................................................................
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