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Kinetic Simulation, Sensitivity Analysis of Fission Product Activity and Source Term Evaluation for Typical Accident Scenarios in Nuclear Reactors

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Kinetic Simulation, Sensitivity Analysis of Fission Product Activity and Source Term Evaluation for Typical Accident Scenarios in Nuclear Reactors KINETIC SIMULATION, SENSITIVITY ANALYSIS OF FISSION PRODUCT ACTIVITY AND SOURCE TERM EVALUATION FOR TYPICAL ACCIDENT SCENARIOS IN NUCLEAR REACTORS SAEED EHSAN AWAN Department of Physics & Applied Mathematics Pakistan Institute of Engineering and Applied Sciences Islamabad 45650, Pakistan 2012 KINETIC SIMULATION, SENSITIVITY ANALYSIS OF FISSION PRODUCT ACTIVITY AND SOURCE TERM EVALUATION FOR TYPICAL ACCIDENT SCENARIOS IN NUCLEAR REACTORS SAEED EHSAN AWAN A dissertation submitted in partial fulfillment of the requirements for the degree of Doctor of Philosophy Department of Physics & Applied Mathematics Pakistan Institute of Engineering and Applied Sciences Islamabad 45650, Pakistan June, 2012 Starting with the name of Allah, the Most Gracious, the Most Merciful Declaration of originality I hereby declare that the work contained in this thesis and the intellectual contents of this report are the product of my own work. This report has not been previously published in any form nor does it contain any verbatim of the published resources which could be treated as infringement of the international copy law. I also declare that I do understand the terms ‘copyright’ and ‘plagiarism’ and that in case of any copyright violation or plagiarism found in this work, I will be held fully responsible of the consequences of any such violation. Signature: _________________ Author’s Name: Saeed Ehsan Awan CERTIFICATE Certified that work contained in thesis entitled KINETIC SIMULATION, SENSITIVITY ANALYSIS OF FISSION PRODUCT ACTIVITY AND SOURCE TERM EVALUATION FOR TYPICAL ACCIDENT SCENARIOS IN NUCLEAR REACTORS was carried out by Mr. Saeed Ehsan Awan under our supervision, and that, in our opinion, it is fully adequate in scope and quality, for the award of degree of Doctor of Philosophy. __________________ __________________ Dr Nasir M. Mirza Dr Sikander M. Mirza Supervisor, Co-Supervisor, Department of Physics and Department of Physics and Applied Mathematics, Applied Mathematics, PIEAS Nilore, Islamabad PIEAS Nilore, Islamabad This Thesis was reviewed by: I. Prof. Dr. Brent. J. Lewis, Department of Chemistry & Chemical Engineering, Royal Military College of Canada. II. Prof. Dr. Sung Oh Cho, Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology (KAIST). III. Dr. Waheed Arshad, Head SSDL, HPD PINSTECH (Local-Examiner) IV. Dr. Nasim Irfan, Head DNE, PIEAS, Nilore (Local-Examiner) V. Dr. Mansoor. H. Inayat, Head DCHE, PIEAS, Nilore (Local-Examiner) Submitted Through: __________________ Dr. Masroor Ikram Head of Department, Department of Physics and Applied Mathematics, Pakistan Institute of Engineering and Applied Sciences (PIEAS) Dedicated To My Mother Who Prayed for my success since I have been in my Early school days and motivated me throughout her life. I will always remember her as a beacon of light in my life and pray to ALLAH Almighty to forgive her shortcomings as a human being and award her Janna-tul-Firdaws (Ameen) Acknowledgements All praises to Almighty ALLAH, the almighty, the most gracious and the most merciful who gave me the strength, power and wisdom necessary to accomplish this task. I would like to offer humblest thanks from the core of my heart to the holy Prophet MUHAMMAD (peace be upon him) who is forever a model of guidance and knowledge for humanity. It is my pleasure to express my deepest gratitude to my Advisor Dr. Nasir M. Mirza for their consistent encouragement, technical advice, constructive criticism, guidance, enthusiasm and invaluable ideas throughout my PhD studies and research. I do thank my Co-Advisor Dr. Sikander M. Mirza who saved no effort to provide all of his scientific and technical experience for me. I would like to thank him for the many fruitful discussions and for helping me to organize my thoughts in writing this thesis. I wish to become a human with qualities that both of my advisors have. Special thanks are also due to all of my teachers at PIEAS and elsewhere who have contributed and supported me throughout my academic carrier. Thanks to technical staff of DPAM and computer centre at PIEAS, for their generous technical support. I am truly grateful to my parents, brothers, sisters, wife and son, Khurram Saeed for their patience; prayers and encouragement without which this whole work would have remained a dream. I would like to pay my deepest gratitude to my mother who is no more in this world. Her encouraging support is memorial asset of my life. I cannot forget the support of my friends Malik Sajjad Mehmood, Manzoor Ahmed, Asif Mehmood, Malik Azhar Hussain, Ahmat Khurshid, Ehtashm-ul-Haq, Matiullah Shah, Yaqoob Khan, Muhammad Anwar, Khurram Jawad, Javid Iqbal, Fazal Badshah, Muhammad Sohail, Sana Ullah, Dr Rafi Ullah & Dr Fakhar. Specials thanks are due to my friend Adnan Idris, who helped me a lot in writing up of thesis. Without his advice, and excellent assistance, this thesis write up could have been much more difficult. Finally, I gratefully acknowledge the financial support of the Higher Education Commission (HEC), Pakistan for the Ph.D. (Indigenous) fellowship under Grant # 17-5- 3(PS3-177)/HEC/Ind-Sch/2006/Phase-III. SAEED EHSAN AWAN PIEAS, Nilore, Islamabad vii List of Publications This thesis consists of following publications 1. Saeed Ehsan Awan, Sikander M. Mirza, Nasir M. Mirza. “Sensitivity Analysis of Fission Product Activity in Primary Coolant of Typical PWRs”, Progress in Nuclear Energy, Vol. 53, 245-249, (2011). 2. Sana Ullah, Saeed Ehsan Awan, Nasir M. Mirza, Sikander M. Mirza. “Source Term Evaluation for the Upgraded LEU Pakistan Research Reactor-1 Under Severe Accidents”. Nuclear Engineering & Design, Vol. 240, 3740-3750 (2010). 3. Sana Ullah, Saeed Ehsan Awan, Nasir M. Mirza, Sikander M. Mirza, “Modeling and Simulation of Release of Radioactivity from a Typical MTR Type Research Reactor Under Accidental Conditions”. IEEE 13th International Multi topic Conference, 2009. INMIC 2009. 4. Saeed Ehsan Awan, Nasir M. Mirza, Sikander M. Mirza, “Kinetic Study of Fission Product Activity Released inside Containment Under Loss of Coolant Accident in a Typical MTR System”. Applied Radiation and Isotopes (Submitted), 2012. viii Table of Contents Acknowledgement……………………………………………………………………....vii List of Publications……………………………………………………………………...viii List of Figures……………………………………………………………………….......xiii List of Tables…………………………………………………………………………....xvi Abstract…………………………………………………………………………….......xviii CHAPTER 1 ...................................................................................................................... 1 Introduction 1.1 Objectives .............................................................................................................. 11 1.2 Thesis Layout ......................................................................................................... 14 CHAPTER 2 .................................................................................................................... 16 Literature Review 2.1 Background ............................................................................................................ 16 2.2 Review of Sensitivity Analysis in Nuclear System ............................................... 40 2.3 Source Term Evaluation for Nuclear Systems ....................................................... 44 2.4 Reactor Description ............................................................................................... 45 2.5 Nature of the Problem ............................................................................................ 49 2.6 Chapter Summary .................................................................................................. 50 CHAPTER 3 .................................................................................................................... 51 Mathematical Model and Computer Implementation 3.1 Fission Products activity in Primary coolant ......................................................... 51 3.1.1 Fission Product Production ......................................................................... 51 3.1.2 Fission Products Behavior in Fuel .............................................................. 52 3.1.3 Fission Products Behavior in the Fuel Pellet .............................................. 52 3.2 Fission Products in PWRs ...................................................................................... 56 ix 3.3 Mathematical Formulation ..................................................................................... 61 3.4 Calculation Methodology....................................................................................... 63 3.5 FPCART Program Description .............................................................................. 66 3.6 Numerical Simulation Techniques ......................................................................... 68 3.6.1 Single Step Methods ................................................................................... 68 3.6.2 Multi-Step Methods .................................................................................... 68 3.6.3 Numerical Solutions of ODEs by Using One Step Methods ...................... 68 3.7 Numerical Solutions of ODE by using Runge- Kutta (RK4) Method ................... 69 3.7.1 Algorithm for the fourth order Runge- Kutta Method ................................ 71 3.8 Source Term Estimation for Nuclear Systems ....................................................... 72 3.9 Factors Effecting the Source Term .......................................................................
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