Nuclear Systems Volume II: Elements of Thermal Hydraulic Design (Hardcover)
暫譯: 核系統第二卷：熱水力設計要素（精裝版）

這本書深入探討核電廠中各種熱流體系統和技術，包括最新反應爐設計及其熱/流體技術的討論。除了核反應爐核心的熱水力設計和分析外，書中還涵蓋了核電廠的其他組件，如加壓器、圍護結構以及整個主要冷卻系統。

本書更強調透過計算流體力學對速度和溫度場進行小尺度解析的適當模型，並展示這如何提高核電廠預測操作條件的準確性。它介紹了縮放法則和不確定性分析的考量，並更廣泛地涵蓋了事故中遇到的現象。

特色

- 討論反應爐中宏觀和微觀流動條件的各種建模方法的基本概念
- 涵蓋特定設計考量，如自然對流和核心可靠性
- 使讀者更好地理解安全考量在熱工程和現代核電廠分析中的重要性
- 每章末尾設有問題
- 包含供採用的講師使用的解答手冊

這本書作為核工程高年級本科生和研究生的教科書，適用於學習核電廠中的熱/水力系統的課程。

Neil E. Todreas is a Professor Emeritus in the Departments of Nuclear Science and Engineering and Mechanical Engineering at the Massachusetts Institute of Technology. He held the Korea Electric Power Corporation (KEPCO) chair in nuclear engineering from 1992 until his retirement to part- time activities in 2006. He served an 8-year period from 1981 to 1989 as the Nuclear Engineering Department Head. Since 1975, he has been a codirector of the MIT Nuclear Power Reactor Safety summer course, which presents current issues of reactor safety significant to an international group of nuclear engineering professionals. His area of technical expertise includes thermal and hydraulic aspects of nuclear reactor engineering and safety analysis. He started his career at Naval Reactors working on the Shippingport reactor and surface nuclear vessels after earning a BEng and an MS in Mechanical Engineering at Cornell University. Following his ScD in Nuclear Engineering at MIT, he worked for the Atomic Energy Commission (AEC) on organic-cooled/heavy water-moderated and sodium-cooled reactors until he returned as a faculty member to MIT in 1970. He has an extensive record of service for government (Department of Energy (DOE), U.S. Nuclear Regulatory Commission (USNRC) and national laboratories), utility industry review committees including INPO, and international scientific review groups. He has authored more than 250 publications and a reference book on safety features of light water reactors. He is a member of the U.S. National Academy of Engineering and a fellow of the American Nuclear Society (ANS) and the American Society of Mechanical Engineers (ASME). He has received the American Nuclear Society Thermal Hydraulics Technical Achievement Award, its Arthur Holly Compton Award in Education, and its jointly conferred (with the Nuclear Energy Institute) Henry DeWolf Smyth Nuclear Statesman Award.

Mujid S. Kazimi was a Professor in the Departments of Nuclear Science and Engineering and Mechanical Engineering at the Massachusetts Institute of Technology. He was the first director of the Center for Advanced Nuclear Energy Systems (CANES) and the Tokyo Electric Power Company (TEPCO) chair professor in Nuclear Engineering both at MIT. Prior to joining the MIT faculty in 1976, Dr. Kazimi worked for a brief period at the Advanced Reactors Division of Westinghouse Electric Corporation and at Brookhaven National Laboratory. At MIT, he was Head of the Department of Nuclear Engineering from 1989 to 1997 and Chair of the Safety Committee of the MIT Research Reactor from 1998 to 2009. He served from 1990 to 2015 as the codirector of the MIT Nuclear Power Reactor Safety summer course. He was active in the development of innovative designs of fuel and other components of nuclear power plants and in analysis of the nuclear fuel cycle options for sustainable nuclear energy. He co-chaired the 3-year MIT interdisciplinary study on the Future of the Nuclear Fuel Cycle, published in 2011. He served on scientific advisory committees at the U.S. National Academy of Engineering and several other national agencies and laboratories in the United States, Japan, Spain, Switzerland, Kuwait, the United Arab Emirates and the International Atomic Energy Agency. He authored more than 200 articles and papers that have been published in journals and presented at international conferences. Dr. Kazimi earned a BEng at Alexandria University in Egypt and an MS and PhD at MIT, all in Nuclear Engineering. He was a fellow of the American Nuclear Society and the American Association for the Advancement of Science. Among his honors is the Technical Achievement Award in Thermal Hydraulics by the American Nuclear Society and membership in the U.S. National Academy of Engineering.

Mahmoud Massoud is an adjunct Professor at the Department of Mechanical Engineering, University of Maryland, College Park, where he has taught undergraduate and graduate level engineering courses since 1988. Dr. Massoud has been active in the Nuclear Industry as a Principal Engineer at the Exelon Corporation and as a Consulting Engineer since 1989. He has authored a textbook in engineering and over 20 journal and conference papers. Dr. Massoud earned his B.S. and M.S. in Mechanical Engineering with emphasis in Internal Combustion Engines from Tehran University. Subsequently, he earned his M.S. and Nuclear Engineer's degree from MIT's Mechanical and Nuclear Engineering Departments, respectively. He earned his Ph.D. in Nuclear Engineering from the University of Maryland College Park.

Neil E. Todreas 是麻省理工學院核科學與工程系及機械工程系的名譽教授。他於1992年至2006年退休前擔任韓國電力公司（KEPCO）核工程講座教授。他在1981年至1989年間擔任核工程系主任。自1975年以來，他一直是麻省理工學院核電反應堆安全暑期課程的共同主任，該課程針對國際核工程專業人士介紹反應堆安全的當前議題。他的技術專長包括核反應堆工程和安全分析的熱力學和流體力學方面。他的職業生涯始於海軍反應堆，參與Shippingport反應堆和表面核艦艇的工作，並在康奈爾大學獲得機械工程的學士和碩士學位後，於麻省理工學院獲得核工程的科學博士學位。隨後，他在原子能委員會（AEC）工作，專注於有機冷卻/重水調節和鈉冷卻反應堆，直到1970年回到麻省理工學院擔任教職。他在政府（能源部（DOE）、美國核能監管委員會（USNRC）和國家實驗室）、公用事業行業審查委員會（包括INPO）和國際科學審查小組中有著廣泛的服務記錄。他已發表超過250篇出版物和一本關於輕水反應堆安全特徵的參考書。他是美國國家工程院的成員，也是美國核學會（ANS）和美國機械工程師學會（ASME）的會士。他獲得了美國核學會熱力學技術成就獎、亞瑟·霍利·康普頓教育獎，以及與核能研究所共同頒發的亨利·德沃夫·史邁斯核國家元首獎。

穆吉德·S·卡齊米（Mujid S. Kazimi）曾是麻省理工學院核科學與工程系及機械工程系的教授。他是麻省理工學院先進核能系統中心（CANES）的首任主任，以及東京電力公司（TEPCO）核工程講座教授。在1976年加入麻省理工學院教職之前，卡齊米博士曾在西屋電氣公司先進反應堆部門和布魯克海文國家實驗室工作過一段時間。在麻省理工學院，他於1989年至1997年擔任核工程系主任，並於1998年至2009年擔任麻省理工學院研究反應堆安全委員會主席。他於1990年至2015年擔任麻省理工學院核電反應堆安全暑期課程的共同主任。他積極參與核電廠燃料及其他組件的創新設計開發，以及可持續核能的核燃料循環選項分析。他共同主持了為期三年的麻省理工學院跨學科研究，研究核燃料循環的未來，並於2011年發表。他曾在美國國家工程院及美國、日本、西班牙、瑞士、科威特、阿聯酋和國際原子能機構的多個國家機構和實驗室的科學諮詢委員會任職。他已發表超過200篇文章和論文，並在國際會議上進行報告。卡齊米博士在埃及亞歷山大大學獲得學士學位，並在麻省理工學院獲得核工程的碩士和博士學位。他是美國核學會和美國科學促進會的會士。他的榮譽包括美國核學會熱力學技術成就獎和美國國家工程院的會員資格。

Mahmoud Massoud 是馬里蘭大學帕克分校機械工程系的兼任教授，自1988年以來教授本科和研究生層級的工程課程。馬斯烏德博士自1989年以來在核工業擔任Exelon Corporation的首席工程師和顧問工程師。他已撰寫一本工程教科書以及超過20篇期刊和會議論文。馬斯烏德博士在德黑蘭大學獲得內燃機專業的機械工程學士和碩士學位。隨後，他分別在麻省理工學院的機械工程和核工程系獲得碩士和核工程師學位。他在馬里蘭大學帕克分校獲得核工程的博士學位。