Nuclear Fuel Cycle

本書描述了整個核燃料循環的不同階段中涉及的各種過程，包括鈾、釷和其他核材料的勘探、礦石的開採和磨粉、分離核材料轉換為核級材料、製造不同類型的核燃料及其物理和化學質量控制、反應堆運行期間燃料與裂變產物之間的熱力學相互作用、後照射檢查、用過燃料再處理、放射性廢物管理、核材料核算和控制，以及處理和運輸核材料所涉及的安全方面。本書為實踐中的核科學家和工程師、年輕研究人員以及對從事核科學和技術領域的人力資源開發感興趣的研究生提供了基礎知識。它也可以作為研究生課程《核燃料循環》的教材。

Prof. B. S. Tomar is presently Institute Chair Professor at Homi Bhabha National Institute (HBNI), Mumbai. He joined the Radiochemistry Division of Bhabha Atomic Research Centre (BARC), Mumbai, in 1982. He is an expert in nuclear and radiochemistry, radiation detection and measurement, and non-destructive assay of nuclear materials and has published more than 220 research papers in international journals. He has taught the subject of nuclear and radiochemistry at postgraduate level for over 25 years. He superannuated as Director Radiochemistry and Isotope Group, BARC, in December 2017 and later served as Raja Ramanna Fellow, DAE, during 2018-2021. He was Visiting Professor to Technical University, Delft, The Netherlands, during 2007-2008 and Member of the Standing Advisory Group on Safeguards Implementation (SAGSI), IAEA, during 2016-2017.

Prof. P. R. Vasudeva Rao was the Vice Chancellor of Homi Bhabha National Institute (HBNI), a Deemed-to-be University under theDepartment of Atomic Energy(DAE), India till recently. He earlier served as Scientific Officer with Indira Gandhi Centre for Atomic Research (IGCAR) at Kalpakkam and was its Director, at the time of his superannuation. He obtained his Ph.D. degree in Chemistry from University of Bombay in 1979 for his work on chemistry of actinide elements. Prof. Rao is an expert in Fuel Cycle Chemistry and especially chemistry of fast reactor fuel cycle and is well known for his research on actinide separations. He was responsible for the development of several facilities for R&D on fast reactor fuel cycle at IGCAR. He has over 300 publications in peer-reviewed international journals. He is a Fellow of the Indian National Academy of Engineering as well as the National Academy of Sciences, India.

Dr. S. B. Roy pursued her B.Tech. in Chemical Engineering from Calcutta University in 1981 and obtained doctorate degree in Chemical Engineering from Indian Institute of Technology (IIT) Bombay in 2001. She joined the 25th batch of BARC training school in 1981 and later joined Uranium Extraction Division of BARC in 1982. She was instrumental in development of uranium fuel of different grades for special applications, process for recovery of uranium from secondary sources like monazite, research, facility development and production management of specific quality nuclear fuel materials for various Indian Research Reactors, and development and implementation of largescale metallothermic reduction processes for Nuclear Grade Uranium Metal production. As Director of Chemical Engineering Group, she provided strategic direction, technical guidance, and human resource development to the implementation of various programs undertaken by different divisions of the group in the areas of nuclear materials. Additionally, she provided guidance to other units of DAE on research and project activities as Member of Nuclear Fuel Complex Board (NFC, Hyderabad) and Heavy Water Board (HWB, Mumbai). Post superannuation, she served as Raja Ramanna Fellow, DAE, and later as Visiting Scientist till November 2020, wherein she contributed in the field of Safety Review and Human Resource Development.

Dr. Jose P. Panakkal joined Bhabha Atomic Research Centre from 16th batch of training school and had been working at BARC in various capacities for 40 years. He superannuated as Head, Advanced Fuel Fabrication Facility, Nuclear Fuels Group, BARC, and was awarded Raja Ramanna Fellowship by DAE on superannuation. He also had worked as Guest Scientist at Fraunhofer Institute of NDT, Saarbrucken, Germany (1987-89). He was recognized as Ph.D. Guide by Mumbai University and Homi Bhabha National Institute (HBNI). He is specialized in the fabrication of nuclear fuels particularly containing plutonium for both thermal and fast reactors and was in charge of an industrial scale MOX (Mixed Oxide) fuel fabrication facility which has made MOX fuels for various types of reactors (BWRs, PHWRs, and fast reactors). He has also developed new techniques for fabrication, quality control, and non-destructive evaluation of nuclear fuels and material characterization as evident from his 280 publications including 130 publications in international journals and conferences.

Shri Kanwar Raj graduated with honors in Chemical Engineering in 1972 from Indian Institute of Technology Roorkee, India. Since then, he has worked in the various capacities in the field of design, research & development, operations, and safety analysis of radioactive waste management plants/ facilities. Shri Raj has extensive expertise in design, commissioning, and operation of high-level radioactive vitrification systems as well as in evaluation of long-term performance of vitrified waste product under geological disposal conditions. As Chief Scientific Investigator, he has led two BARC teams for studies in this area in collaboration with Kfk /INE Karlsruhe and as apart of coordinated research program of IAEA, Vienna. As Head, Waste Management Division, BARC, Mr. Raj supervised operations of Waste Management Facilities at Kalpakkam, Tarapur, and Trombay Centres of the Department of Atomic Energy, India. He has gained hands-on experience in management of radioactive waste generations from the entire nuclear fuel cycle, viz. radiochemical laboratories, fuel fabrication facilities, research/power reactors, reprocessing plants, etc. His expertise also encompasses management of spent radiation sources from various industries, medical centers, and research institutions. Mr. Raj has experience in preparation of National and International Waste Safety Standards for Indian Atomic Energy Regulatory Board and IAEA. He is the author/co-author of about 80 research papers published in various journals.

A.N.Nandakumar, a Ph.D. in Physics from Mumbai University, has 34 years of R&D experience in the Bhabha Atomic Research Centre, Mumbai, India, in the fields of safe transport of radioactive material, calculation of radiation shielding, and calculation of radiation dose under normal and emergency conditions involving radioactive material. He was Chief Scientific Investigator from India for the IAEA Coordinated Research Projects on Development of PSA techniques relating to the Safe of Radioactive Material and on Collection of Accident Data for Quantification of Risk in Transport of Radioactive Material. Subsequently, he was appointed Head, Radiological Safety Division, Atomic Energy Regulatory Board, Mumbai. He worked as Transport Safety Specialist and as Consultant in the Radiation, Transport and Waste Safety Division, IAEA, Vienna. He has published over 60 scientific and technical papers in national/international scientific journals and conference proceedings.

Prof. B. S. Tomar目前是孟買的Homi Bhabha國家研究所(HBNI)的院士主席教授。他於1982年加入了孟買的巴巴原子能研究中心(BARC)的放射化學部門。他是核化學、放射性檢測和測量以及核材料非破壞性評估方面的專家，並在國際期刊上發表了220多篇研究論文。他已在研究生階段教授核化學和放射化學科目超過25年。他於2017年12月退休，之後在2018年至2021年期間擔任拉賈·拉曼納研究員。他曾於2007年至2008年期間擔任荷蘭代爾夫特理工大學的客座教授，並於2016年至2017年期間擔任國際原子能機構(IAEA)的保障實施常設諮詢小組(SAGSI)成員。

Prof. P. R. Vasudeva Rao曾是印度原子能部門(DAE)下的Homi Bhabha國家研究所(HBNI)的副校長，該校是一所被視為大學的機構。他曾在卡爾帕坎的英迪拉·甘地原子能研究中心(IGCAR)擔任科學官員，並在退休時擔任該中心的主任。他於1979年在孟買大學獲得化學博士學位，研究領域為錒系元素的化學。Rao教授是燃料循環化學的專家，尤其是快中子反應堆燃料循環的化學，以及他在錒系元素分離方面的研究而聞名。他負責在IGCAR開發了多個快中子反應堆燃料循環的研發設施。他在同行評審的國際期刊上發表了300多篇論文。他是印度國家工程學院和印度國家科學院的院士。

Dr. S. B. Roy於1981年在加爾各答大學獲得化學工程學士學位，並於2001年在孟買的印度理工學院(IIT)獲得化學工程博士學位。她於1981年加入了巴巴原子能研究中心的培訓學校第25屆，並於1982年加入了巴巴原子能研究中心的鈾提取部門。她在開發不同級別的鈾燃料用於特殊應用、從獨居石等次生來源回收鈾、為印度各種研究反應堆開發和生產特定質量的核燃料材料、以及開發和實施大規模金屬熱還原法生產核級鈾金屬等方面發揮了重要作用。作為化學工程組的主任，她為該組的不同部門在核材料領域的各項計劃提供了戰略方向、技術指導和人力資源發展。此外，她作為核燃料複合材料(NFC, Hyderabad)和重水委員會(HWB, Mumbai)的成員，為DAE的其他單位在研究和項目活動方面提供指導。退休後，她擔任拉賈·拉曼納研究員，並在2020年11月之前擔任訪問科學家，為安全審查和人力資源發展領域做出了貢獻。

Dr. Jose P. Panakkal於第16屆培訓學校加入了巴巴原子能研究中心，並在該中心擔任各種職務長達40年。他在退休時擔任巴巴原子能研究中心核燃料組的先進燃料製造設施主任，並獲得了DAE頒發的拉賈·拉曼納研究員獎。他還曾在德國薩爾布呂肯的Fraunhofer無損檢測研究所擔任客座科學家(1987-89)。他被孟買大學和Homi Bhabha國家研究所(HBNI)認定為博士生導師。他專門從事包含鈽的核燃料的製造，特別是熱中子反應堆和快中子反應堆的燃料製造，並負責一個工業規模的MOX(混合氧化物)燃料製造設施，該設施為各種類型的反應堆(BWR、PHWR和快中子反應堆)生產了MOX燃料。