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Scaling Analysis of the Osu High Temperature Test Facility During a Pressurized Conduction Cooldown Event Using Relap5- 3D

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Scaling Analysis of the Osu High Temperature Test Facility During a Pressurized Conduction Cooldown Event Using Relap5- 3D AN ABSTRACT OF THE THESIS OF Juan A. Castañeda for the degree of Master of Science in Nuclear Engineering presented on May 21, 2014. Tittle: SCALING ANALYSIS OF THE OSU HIGH TEMPERATURE TEST FACILITY DURING A PRESSURIZED CONDUCTION COOLDOWN EVENT USING RELAP5- 3D Abstract approved: Brian G. Woods In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear Plant (NGNP) would be the VHTR. The VHTR was chosen because it has the capability to produce electricity, hydrogen and may be used for other high-temperature process heat applications. In support of licensing and validation of the VHTR, Oregon State University was tasked to develop a high temperature apparatus that will be able to capture the thermal fluids phenomena of the VHTR and perform integral effects tests for validation of existing safety codes. The design has been called the High Temperature Test Facility (HTTF), which is a scaled design of the Modular High Temperature Gas-Cooled Reactor (MHTGR). The objective of this study was to investigate the ability of the HTTF to simulate the Pressurized Conduction Cooldown (PCC) Event during the natural circulation phase in the MHTGR. This was achieved with the aid of a thermal hydraulic systems code, RELAP5-3D. ©Copyright by Juan A. Castañeda May 21, 2014 All Rights Reserved SCALING ANALYSIS OF THE OSU HIGH TEMPERATURE TEST FACILITY DURING A PRESSURIZED CONDUCTION COOLDOWN EVENT USING RELAP5-3D by Juan A. Castañeda A THESIS Submitted to Oregon State University in partial fulfillment of the requirements for the degree of Master of Science Presented May 21, 2014 Commencement June 2014 Master of Science thesis of Juan A. Castañeda presented on May 21, 2014. 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 thesis will become part of the permanent collection of Oregon State University libraries. My signature below authorizes release of my thesis to any reader upon request. ______________________________________________________________________________ Juan A. Castañeda, Author ACKNOWLEDGEMENTS The author would like to express his appreciation to all those who somehow contribute to the success of this project. I wish to begin acknowledging and thanking my advisor, Dr. Brian Woods, for giving me the opportunity to work under his guidance. The professional development that I have experienced under his guidance and the willingness to assist me at the times when I needed it the most is invaluable. I greatly appreciate for what he has done and for preparing me for my future outcomes as an engineer. I also would like to express my appreciation to Dr. Wade Marcum for always being willing to answer questions related to my work and providing guidance throughout my graduate studies. Also, I would like to thank Dr. Todd Palmer for taking the time from his busy schedule to be part of my committee and providing valuable feedback through my thesis defense. Also, in no particular order, I would like to express my appreciations to my fellow graduate students Matt Hertel, Jordan Cox, Luke Harmon, Mike Holton, Trever Howard, Mario Gomez, Ruirui Liu, Renae Lenhof, Jackson Harter and Etienne Mullen for their support and encouragement throughout my graduate studies. I also would like to recognize and express my appreciations to Dr. Kathryn Higley for giving me the opportunity to attain my graduate studies at OSU. The knowledge and the learning that I have experience in my short time at OSU are unmatched. I also wish to acknowledge and thank my undergraduate professors, Dr. David Simpson, Dr. Nathaniel Greene and Dr. Nazafarin Fallahian for expressing your trust and guiding me into the right direction to pursue further education. Finally, I would like to thank my parents, Luis and Gilda, and my sister, Evelyn, whose love and support have given me the courage and perseverance to believe in myself in order to chase my dreams. TABLE OF CONTENTS Page 1 INTRODUCTION ........................................................................................................ 1 1.1 Overview ......................................................................................................................... 2 1.1.1 The MHTGR ...................................................................................................... 3 1.1.2 The HTTF ........................................................................................................... 8 1.2 Motivation of Study ....................................................................................................... 11 1.3 Research Objectives ...................................................................................................... 12 1.4 Assumptions .................................................................................................................. 13 1.5 Limitations ..................................................................................................................... 13 1.6 Overview of the Following Chapters ............................................................................. 14 2 LITERATURE REVIEW ........................................................................................... 15 2.1 Postulated Accident Scenarios ....................................................................................... 15 2.1.1 Loss of Forced Convection Accidents .............................................................. 16 2.1.2 Reactivity, Steam Water Ingress and Plant Coupling Events ........................... 17 2.2 The Pressurized Conduction Cooldown Event .............................................................. 18 2.3 Previous Relevant Literatures ........................................................................................ 20 3 HTTF SCALING PARAMETERS ............................................................................. 28 3.1 Single-Phase Natural Circulation Loop Scaling Analysis ............................................. 28 3.2 Single-Phase Fluid Natural Circulation Loop Scaling Ratios ....................................... 32 3.3 Primary Loop Resistance ............................................................................................... 35 3.4 Structural Materials Heat Transfer ................................................................................ 36 3.5 HTTF Design Specifications ......................................................................................... 43 3.5.1 Scaling Choices ................................................................................................ 43 3.5.2 Natural Circulation Design Specifications ....................................................... 44 3.5.3 Structural Materials Design Specifications ...................................................... 46 3.5.4 HTTF Scaling Ratios ........................................................................................ 51 4 DESCRIPTION OF THE RELAP5-3D MODELS .................................................... 55 4.1 The MHTGR ................................................................................................................. 55 TABLE OF CONTENTS (Continued) Page 4.2 The HTTF ...................................................................................................................... 59 4.3 Benchmarking of the Models at Steady-State ............................................................... 64 5 PCC EVENT SIMULATIONS AND RESULTS ....................................................... 74 5.1 Scenario 1: PCC Event with SG Heat Removal ............................................................ 75 5.1.1 Case 1 Specifics ................................................................................................ 75 5.1.2 Case 1 Results ................................................................................................... 75 5.2 Scenario 2: PCC Event with SG and Cross-Duct Vessel Break .................................... 82 5.2.1 Case 2 Specifics ................................................................................................ 82 5.2.2 Case 2 Results ................................................................................................... 84 5.3 Scenario 3: PCC Event with an Isolated Reactor Vessel ............................................... 89 5.5.1 Case 3 Specifics ................................................................................................ 89 5.5.2 Case 3 Results ................................................................................................... 91 5.4 Scenarios Conclusion .................................................................................................... 95 6 HTTF SENSITIVITY STUDIES ................................................................................ 98 6.1 Methods to Preserved Similarity in the HTTF .............................................................. 98 6.1.1 Reducing Natural Convection .........................................................................
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