Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, Third Edition
暫譯: 核系統 第卷：熱流體基礎，第三版

《核能系統，第 I 卷：熱液力學基礎（第三版）》提供了對核能的深入介紹，重點在於核反應堆及其他關鍵核電廠組件的熱液力學設計與分析。作者強調流體流動與熱傳遞的整合，應用於所有類型的電力反應堆及能源來源分配。內容涵蓋核反應堆的概念與系統，包括第三代增強型（GEN III+）、第四代（GEN IV）及小型模組化反應堆（SMR）以及新的發電循環。文本中包含新的章節範例和問題，使用概念參數、全彩文本和插圖、計算機程序、圖表幻燈片以及解答手冊。

特色

- 嚴謹涵蓋核能發電的基本原理
- 描述和分析最新的核電廠設計和技術
- 每章提供廣泛的範例，以說明所呈現的分析方法
- 新增全彩插圖和文本特徵，以增強主題的呈現
- 整合流體流動與熱傳遞，應用於單相和兩相冷卻劑

讀者將發展出改善下一代核反應堆所需的知識和設計技能。

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.

尼爾·E·托德瑞斯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。他在康奈爾大學獲得機械工程學士和碩士學位後，開始在海軍反應堆工作，參與Shippingport反應堆和表面核艦艇的相關工作。隨後，他在麻省理工學院獲得核工程的科學博士學位後，曾在原子能委員會（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）及國家實驗室）、公用事業行業審查委員會（包括INPO）及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篇出版物及一本關於輕水反應堆安全特徵的參考書籍。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。他曾獲得美國核學會熱流體技術成就獎、亞瑟·霍利·康普頓教育獎及與核能研究所共同頒發的亨利·德沃爾夫·史邁斯核國家元首獎。

穆吉德·S·卡齊米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的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。他在1990年至2015年間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、阿聯酋及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機械工程學士學位，並在麻省理工學院獲得核工程的碩士和博士學位。他是美國核學會及美國科學促進會的會士。他的榮譽包括美國核學會熱流體技術成就獎及美國國家工程院的會員資格。