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Passive Safety Injection System Design and Simulation for Small Scale Pressurized Water Reactor

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Passive Safety Injection System Design and Simulation for Small Scale Pressurized Water Reactor Passive Safety Injection System Design and Simulation for Small Scale Pressurized Water Reactor Muhammad Tahir A dissertation submitted for the degree of “Doctor of Philosophy” (PhD) in Pakistan Institute of Engineering and Applied Sciences Islamabad Pakistan May 2011 Declaration I declare that all material in this thesis which is not my own work has been identified and that no material has previously been submitted and approved for the award of a degree in this or in any other university. Signature: __________________________ Author’s Name: (Muhammad Tahir) Supervisor Dr. Imran Rafiq Chughtai Principal Engineer Department of Chemical and Materials Engineering Pakistan Institute of Engineering and Applied Sciences [PIEAS] Islamabad, Pakistan. Head, DNE, PIEAS 2 Acknowledgements All praises and thanks to God, the most Merciful, Compassionate, Gracious and Beneficent who has created man and is a source of knowledge and wisdom. At the very outset, I am thankful to my supervisors, Dr. Imran Rafiq Chughtai, PE and Dr. Muhammad Aslam, CE for their supervision, technical advices throughout the investigations and preparation of this manuscript. I am greatly indebted to director Imtiaz Rabbani for his administrative guidance. I am also grateful to my professors at PIEAS especially Dr. Muhammad Aslam, Dr. Tehsin Hamid, Dr. Naseem Irfan, Dr. Mansoor Hamid Inayat, Dr. Nasir Majid Mirza, Dr. Sikandar Majid Mirza and Dr. Muhammad Tufail. I am thankful to Dr. Muhammad Arfin Khan for his assistance in visiting Texas Tech University USA and guidance in educational and research activities. I am also grateful to my friends and colleagues who ensured a creative and good working environment and helped me in technical and non-technical matters. My special thanks are due to Dr. Munawar Iqbal, and Dr. Basharat Ali. I am also thankful to HEC for grants in favor of foreign visits. I am also thankful to my wife, daughters and sons who have been missing me during my long working hours at PIEAS. I would like to express my dearest feelings towards my parents for their special prayers. At the end, I am grateful to all those who have always wished to see me glittering high on the skies of success, may ALLAH bless them with good health and long lives! Muhammad Tahir 3 PhD research work publications International Publications M. Tahir, I. R. Chughtai and M. Aslam, Qualitative response of SIS for a large size break LOCA in the SRC cold leg, Annals of Nuclear Energy 34(2007) 922- 925. M. Tahir, I. R. Chughtai and M. Aslam, Response of Proposed Passive SIS for an Intermediate Size Break on CHASNUPP-1, Annals of Nuclear Energy 35(2008) 1986-1993. Conference Papers M. Tahir, et al, Proposed Passive SIS for Chasnupp-1 Type Reactors, International Workshop on Passive Safety Systems in Advanced PWRs, 28-30 April 2008, Shanghai Jiao Tong University, Shanghai, China. M. Tahir, et al, Comparative Study of the Passive Safety and the SIS under Loss of Coolant Accident, paper presented in International Conference Spring 2009 Meeting of the Texas Sections of the APS, AAPT, and SPS, 02-04 April 2009, Tarleton State University ,Stephenville, TX, USA. M. Tahir, et al, Simulation of a Passive Safety Injection System for a Small Scale Advance Pressurized Water Reactor Design, paper presented in international conference, Modern trends in physics research, MTPR-10, 12-16 December 2010, Cairo University, Cairo, Egypt. 4 Table of contents LIST OF FIGURES ......................................................................................... 7 LIST OF TABLES ......................................................................................... 10 CHAPTER 1 ................................................................................................. 17 1 INTRODUCTION .................................................................................. 17 1.1 PROBLEM DEFINITION ................................................................................. 19 1.2 RESEARCH OBJECTIVES ................................................................................ 20 1.3 THESIS ORGANIZATION................................................................................ 21 CHAPTER 2 ................................................................................................. 24 2 LITERATURE SURVEY .......................................................................... 24 2.1 REVIEW OF PWR TECHNOLOGY ..................................................................... 24 2.1.1 NPP safety and safety systems ......................................................... 25 2.1.2 Active and passive safety systems ..................................................... 26 2.1.3 Passive safety systems ..................................................................... 27 2.1.4 Applications of passive safety systems in large size reactors ................ 28 2.1.5 Hybrid passive safety systems .......................................................... 31 CHAPTER 3 ................................................................................................. 33 3 MATHEMATICAL MODELING ............................................................... 33 3.1 THREE EQUATION MODEL ............................................................................. 34 3.1.1 Mass balance equation ..................................................................... 34 3.1.2 Momentum balance equation ............................................................ 35 3.1.3 Energy balance equation .................................................................. 36 3.2 FIVE EQUATION MODEL ................................................................................ 36 3.2.1 Mass balance equations ................................................................... 37 3.2.2 Momentum balance equation ............................................................ 37 3.2.3 Energy balance equation .................................................................. 38 3.3 THERMO-HYDRAULIC CORRELATIONS ............................................................... 39 3.4 DECAY HEAT ............................................................................................. 40 5 3.4.1 Fission heat after shutdown .............................................................. 41 3.4.2 Fission product decay Heat ............................................................... 42 3.5 ADVANCE PROCESS SIMULATION ENVIRONMENT ................................................. 43 CHAPTER 4 ................................................................................................. 47 4 NUCLEAR SAFETY SYSTEMS ................................................................ 47 4.1 EMERGENCY CORE COOLING SYSTEM ............................................................... 47 4.1.1 Charging system ............................................................................. 48 4.1.2 Boron injection system ..................................................................... 49 4.1.3 Safety injection system .................................................................... 49 4.1.4 Accumulator injection system ........................................................... 50 4.1.5 Residual heat removal system .......................................................... 51 4.1.6 Role of ECCS during various LOCAs ................................................... 53 4.2 SIMULATION OF EMERGENCY CORE COOLING SYSTEM ........................................... 56 4.2.1 Simulation of reactor trip system ...................................................... 57 CHAPTER 5 ................................................................................................. 71 5 PROPOSED PASSIVE SAFETY SYSTEM ................................................ 71 5.1 THERMAL HYDRAULIC DESIGN OF THE PROPOSED SYSTEM ..................................... 71 5.2 CONTROLS IMPLEMENTED ............................................................................. 76 CHAPTER 6 ................................................................................................. 78 6 PROPOSED SYSTEM APPLICATIONS ................................................... 78 6.1 VALIDATION OF REFERENCE POWER PLANT MODEL .............................................. 78 6.2 PROPOSED PASSIVE SAFETY SYSTEM RESPONSE .................................................. 78 6.2.1 Intermediate break LOCA ................................................................. 79 6.2.2 Proposed system‟s response for large break ....................................... 94 CHAPTER 7 ................................................................................................ 107 7 CONCLUSION AND FUTURE RECOMMENDATIONS ............................. 107 REFERENCES ............................................................................................. 110 APPENDIX ................................................................................................. 114 Reference power plant simulation .............................................................. 114 6 List of Figures Figure 2-1 AP600/AP1000 passive safety systems ..................................... 30 Figure 2-2 AP600/AP1000 containment cooling system .............................. 30 Figure 4-1 Block diagram of charging and boron injection system ............... 48 Figure 4-2 Block diagram of safety injection system ................................... 50 Figure 4-3 Block diagram of accumulator injection system .......................... 51 Figure 4-4 Block diagram of residual heat removal system .........................
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