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Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors

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Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors 0 Department of Nuclear Engineering And Radiation Health Physics DESIGN AND ANALYSIS OF A NUCLEAR REACTOR CORE FOR INNOVATIVE SMALL LIGHT WATER REACTORS. By Alexey I. Soldatov A DISSERTATION Submitted to Oregon State University March 9, 2009 1 AN ABSTRACT OF THE DISSERTATION OF Alexey I. Soldatov for the degree of Doctor of Philosophy in Nuclear Engineering presented on March 9, 2009. Title: Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors. Abstract approved: Todd S. Palmer In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and Reactor Control System shadowing. 2 The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). This section also includes discussion of the parameters important for safety and evaluation of Reactor Control System options for the proposed core design. An evaluation of the sensitivity of the proposed design to uncertainty in calculated parameters is presented in chapter 4-5. The results presented in this dissertation cover a new area of reactor design and operational parameters, and may be applicable to other small and large pressurized water reactor designs. 3 © Copyright by Alexey I. Soldatov March 9, 2009 All Rights Reserved 4 Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors. By Alexey I. Soldatov A DISSERTATION Submitted to Oregon State University in partial fulfillment of the requirements for the degree of Doctor of Philosophy Presented March 9, 2009 Commencement June 2009 5 Doctor of Philosophy dissertation of Alexey I. Soldatov presented on March 9, 2009. APPROVED Major professor, representing Nuclear Engineering Head of the Department of Nuclear Engineering and Radiation Health Physics Dean of the Graduate School I understand that my dissertation will become part of the permanent collection of Oregon State University libraries. My signature below authorizes release of my dissertation to any reader upon request. Alexey I. Soldatov, Author 6 ACKNOWLEDGEMENTS I would like to take this opportunity to thank Dr. Todd S. Palmer for all of his support, ideas and positive input through the research and writing phases of this dissertation. I would like to thank Dr. Kord S. Smith of Studsvik Scandpower, and personnel of this company for guidance and support of this project. I would like to thank the faculty members of Oregon State University Nuclear Engineering and Radiation Health Physics department, and particularly Dr. Jose N. Reyes Jr., Dr. Qiao Wu, Dr. Brian Woods, Dr. Steve Reese Dr. Michael Hartman and dissertation committee members Dr. Goran N. Jovanovic and Dr. Jamie J Kruzic, who have helped me with development of the research concepts and ideas, and writing this dissertation. Also I would like to acknowledge the valuable input into the MASLWR core design from OSU undergraduate and graduate students Mark Galvin, Jeff Dahl, Jeff Magedanz, Wade Marcum, Alex Misner, Sander Marshall and Benjamin Nelson. Their input, comments and ideas were important for the development of the MASLWR concept and for further feasibility studies. I would like to thank my instructors and professors from Moscow Engineering Physics Institute, who guide me through my education and help with information collection and analysis for this dissertation. Finally I would like to acknowledge my family for the inspiration and support in my education, and particularly my father, Igor Mikhailovich Soldatov P.E., who has encouraged me to give my heart and soul into Nuclear Engineering and Science. 7 TABLE OF CONTENTS Page Chapter 1 – Introduction ................................................................................................ 1 1.1. Introduction......................................................................................................... 1 Chapter 2 Literature review ........................................................................................... 3 2.1. Small reactor designs on market (Competitors for MASLWR) ......................... 3 2.2. Innovative LWR research programs and Research Areas................................. 26 2.3. National and International requirements and regulations ................................. 35 Chapter 3 – Methodology ............................................................................................ 43 3.1. Initial Data – Definition of research goals .................................................. 43 3.2. Initial Data – Geometry and materials ........................................................ 44 3.3. Tools Available for Neutronic design......................................................... 47 3.4. Studsvik Scandpower Tools.............................................................................. 48 3.5. Physical Models implemented in the tools ....................................................... 49 3.6. Algorithms of the tools used for the standard calculations............................... 56 3.7. Organization of the feasibility study................................................................. 59 3.8 Goals of Feasibility Study, Criteria of completion ............................................ 69 Chapter 4 Results ......................................................................................................... 70 Chapter 4-1 – Study of the Physical Effects in MASLWR 8% Enriched Fuel (General Analysis) ...................................................................................................................... 71 4-1.1 Calculation model........................................................................................... 71 4-1.2 Multiplication factor ....................................................................................... 73 8 TABLE OF CONTENTS (Continued) Page 4-1.3 Fuel Depletion, Plutonium Production..................................................... 78 4-1.4 Neutron flux and energy spectra for PWR and MASLWR .......................... 100 4-1.5 Prompt neutron lifetime and Effective fraction of delayed Neutrons........... 110 4-1.6. Reactivity Effects......................................................................................... 116 4-1.7. Control Rod Worth, Shielding and Shadowing Effects............................... 133 4-1.8 Conclusions................................................................................................... 157 Chapter 4-2 – Results Gadolinium Burnable Absorbers for MASLWR Fuel ........... 159 4-2.1 Burnable Absorbers (Functions, Design Options)........................................ 159 4-2.2. Calculation Model and Assumptions........................................................... 168 4-2.3. Fuel Assembly with Gadolinium BP (standard geometries). ..................... 170 4-2.4. Self-shielding effects in fuel with burnable absorbers................................. 175 4-2.5. Shadowing effects of Gd burnable absorbers in V and W fuel assembly modifications.......................................................................................................... 187 4-2.6. Control rod shadowing effect ...................................................................... 202 4-2.7. Multiple burnable absorbers for programming of multiplication factor...... 209 4-2.8. Conclusions.................................................................................................. 211 Chapter 4-3 Results – Reflector Studies .................................................................... 213 4-3.1. Basic requirements for a neutron reflector .................................................. 214 4-3.2. Neutron Reflector Materials ........................................................................ 216 4-3.3. Neutron Reflector Geometry ....................................................................... 219 9 TABLE OF CONTENTS (Continued) Page 4-3.4. Reflector Studies with SIMULATE-3 ......................................................... 222 4-3.5. Reflector Studies with CASMO-4E............................................................. 227 4-3.6 Conclusions for Reflector Studies ................................................................ 235 Chapter 4-4 Results – Core Design............................................................................ 236 4-4.1. MASLWR core model in SIMULATE-3 .................................................... 237 4-4.2.
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