上海交通大学研究生课程开设申请表New GraduateCourse ApplicationForm, SJTU课程基本信息BasicInformation（中文Chinese）核工程材料*课程名称Course Name（英文English）NuclearEngineeringMaterials*学分*学时232（1学分≥16课时）CreditsTeaching Hours秋季否*开课学期跨Spanning over个学期*时否跨学期SemesterFallCross-semester?Semesters.专业课全日制*课程性质*课程分类Course CategoryCourse TypeMajor CourseFull-time*授课语言中文ChineseInstructionLanguage*成绩类型等级制LetterGradeGrade(050)材料科学与工程学院*开课院系SchoolSchool of Materials Science & Engineering所属学科Subject姓名Name工号ID单位School联系方式E-mail负责教师 Person in charge沈朝952911809@qq.com课程扩展信息ExtendedInformation课程定位：本课程为重要的材料科学与工程专业选修课，课程以课堂授课为主，以学生研讨为辅，使学生了解主要核反应堆型材料的成分、晶体结构、微观组织结构与材料性能的关系，以及与核安全相关的选材原则。教学目标：分类讲解核工程材料的种类以及其在严苛服役环境下的失效行为及机理，掌握预测结构材料服役寿命、改善反应堆运行条件以及开发新型核工程材料的基础知识。学生大作业及研讨内容包括先进燃料、事故容错燃料材料、先进核反应堆安全相关关键材料技术的发展趋势及研究方法，使学生学会从现象分析问题的本质，抓住问题背后的科学问*课程简介(中文)题，将所学到的核工程材料学知识运用到核工业实践过程。Course Description主要内容：课堂重点介绍先进压水堆主要设备所用的材料及其性能特点，掌握有机、无机氧化物、金属等工程材料在射线和快中子辐照条件下的辐照损伤机理、金属材料在高温高压水环境下的腐蚀机理，了解核燃料、包壳材料、堆内构件、反应堆压力容器、主冷却剂管道、蒸汽发生器传热管等核电厂主要设备及部件的选材原则、失效机理、防范措施等知识。先修课程：《材料科学基础》
上海交通大学研究生课程开设申请表 New Graduate Course Application Form, SJTU 课程基本信息 Basic Information *课程名称 Course Name （中文 Chinese） 核工程材料 （英文 English） Nuclear Engineering Materials *学分 Credits 2 *学时 Teaching Hours 32 （1 学分≥16 课时） *开课学期 Semester 秋季 *时否跨学期 Cross-semester? 否 跨 Spanning over 个 学期 Fall Semesters。 *课程性质 Course Category 专业课 *课程分类 Course Type 全日制 Major Course Full-time *授课语言 Instruction Language 中文 Chinese *成绩类型 Grade 等级制 Letter Grade *开课院系 School (050)材料科学与工程学院 School of Materials Science & Engineering 所属学科 Subject 负责教师 Person in charge 姓名 Name 工号 ID 单位 School 联系方式 E-mail 沈朝 952911809@qq.com 课程扩展信息 Extended Information *课程简介 (中文) Course Description 课程定位：本课程为重要的材料科学与工程专业选修课，课程以课堂授课为主，以学生研 讨为辅，使学生了解主要核反应堆型材料的成分、晶体结构、微观组织结构与材料性能的 关系，以及与核安全相关的选材原则。 教学目标：分类讲解核工程材料的种类以及其在严苛服役环境下的失效行为及机理，掌握 预测结构材料服役寿命、改善反应堆运行条件以及开发新型核工程材料的基础知识。学生 大作业及研讨内容包括先进燃料、事故容错燃料材料、先进核反应堆安全相关关键材料技 术的发展趋势及研究方法，使学生学会从现象分析问题的本质，抓住问题背后的科学问 题，将所学到的核工程材料学知识运用到核工业实践过程。 主要内容：课堂重点介绍先进压水堆主要设备所用的材料及其性能特点，掌握有机、无机 氧化物、金属等工程材料在γ射线和快中子辐照条件下的辐照损伤机理、金属材料在高温高 压水环境下的腐蚀机理，了解核燃料、包壳材料、堆内构件、反应堆压力容器、主冷却剂 管道、蒸汽发生器传热管等核电厂主要设备及部件的选材原则、失效机理、防范措施等知 识。 先修课程：《材料科学基础》
CoursePositioning:Thiscourseisanimportantelectiveinthefieldofmaterialsscienceandengineering,primarilylecture-basedwith supplemental studentseminars.Itaimstofamiliarizestudents with the composition, crystal structure, microstructure, and the relationship between theseaspectsand thematerial properties ofmainnuclearreactortypes,as wellas thematerial selectionprinciplesrelatedtonuclearsafetyEducational Objectives:The course categoricallyexplains thetypes ofnuclear engineeringmaterials and theirfailure behaviors and mechanisms under harsh service conditions.It providesfoundational knowledgefor predicting the service life ofstructural materials, improving reactoroperatingconditions,anddeveloping newnuclearengineeringmaterials.Themajor studentprojectsand seminar topics include advanced fuels, accident-tolerant fuel materials, and the trends andresearch methods in critical material technologies related to advanced nuclear reactor safety.This*课程简介enables studentstoanalyzethe essenceof phenomena,grasp the underlyingscientific issues,and(English)apply theknowledge ofnuclear engineering materials learned to thepractical processes of theCourseDescriptionnuclear industry.Main Content: Thecourse emphasizes the materials and their performance characteristics used inmajorequipmentofadvancedpressurizedwaterreactors,masteringthemechanismsofradiationdamage under gamma rays and fast neutron rradiation conditionsfor organic, inorganic oxides, andmetals.It also covers the corrosion mechanisms of metal materials under high-temperature and high-pressure water environments. Additionally,it addresses the material selection principles,failuremechanisms,andpreventivemeasuresformainnuclearpowerplantequipmentandcomponentssuchas nuclear fuel, cladding materials, in-core components, reactor pressure vessels,primary coolantpipes,and steamgeneratorheattransfertubesPrerequisite Course:"FundamentalsofMaterials Science"课时章节是否有课程思政内容。如章节教学方式主要内容数有，请详述结合我国核电技术从落后到完全自主研发大型先进压水堆“华龙一号”的发展历程，鼓励学生向核电站材料问题21. 绪论课堂教学早期的国内核电领军人才去学及挑战习，要学会志存高远的同时去脚踏实地的解决国家当前面临的卡脖子问题。2.材料的材料的机械、物2课堂教学性质理、化学性质分类和特征、3. 核燃料UO2燃料的堆内*教学大纲2课堂教学材料行为、耐事故燃(中文)料Syllabus锆合金及合金化4.燃料包原理、包壳堆内课堂教学6壳材料性能、耐事故包壳主要部件、性能5.压力容2课堂教学要求、异种材料器材料焊接6.堆内构选材标准、失效件和蒸发2课堂教学行为器材料7.控制材冷却剂、慢化2课堂教学料剂、反射层材料68.材料的辐照损伤机理课堂教学
*课程简介 （English） Course Description Course Positioning: This course is an important elective in the field of materials science and engineering, primarily lecture-based with supplemental student seminars. It aims to familiarize students with the composition, crystal structure, microstructure, and the relationship between these aspects and the material properties of main nuclear reactor types, as well as the material selection principles related to nuclear safety. Educational Objectives: The course categorically explains the types of nuclear engineering materials and their failure behaviors and mechanisms under harsh service conditions. It provides foundational knowledge for predicting the service life of structural materials, improving reactor operating conditions, and developing new nuclear engineering materials. The major student projects and seminar topics include advanced fuels, accident-tolerant fuel materials, and the trends and research methods in critical material technologies related to advanced nuclear reactor safety. This enables students to analyze the essence of phenomena, grasp the underlying scientific issues, and apply the knowledge of nuclear engineering materials learned to the practical processes of the nuclear industry. Main Content: The course emphasizes the materials and their performance characteristics used in major equipment of advanced pressurized water reactors, mastering the mechanisms of radiation damage under gamma rays and fast neutron irradiation conditions for organic, inorganic oxides, and metals. It also covers the corrosion mechanisms of metal materials under high-temperature and high- pressure water environments. Additionally, it addresses the material selection principles, failure mechanisms, and preventive measures for main nuclear power plant equipment and components such as nuclear fuel, cladding materials, in-core components, reactor pressure vessels, primary coolant pipes, and steam generator heat transfer tubes. Prerequisite Course: "Fundamentals of Materials Science" *教学大纲 (中文) Syllabus 章节 主要内容 课时 数 教学方式 章节是否有课程思政内容。如 有，请详述 1. 绪论 核电站材料问题 及挑战 2 课堂教学 结合我国核电技术从落后到完全 自主研发大型先进压水堆“华龙 一号”的发展历程，鼓励学生向 早期的国内核电领军人才去学 习，要学会志存高远的同时去脚 踏实地的解决国家当前面临的卡 脖子问题。 2. 材料的 性质 材料的机械、物 理、化学性质 2 课堂教学 3. 核燃料 材料 分类和特征、 UO2 燃料的堆内 行为、耐事故燃 料 2 课堂教学 4. 燃料包 壳材料 锆合金及合金化 原理、包壳堆内 性能、耐事故包 壳 6 课堂教学 5. 压力容 器材料 主要部件、性能 要求、异种材料 焊接 2 课堂教学 6. 堆内构 件和蒸发 器材料 选材标准、失效 行为 2 课堂教学 7. 控制材 料 冷却剂、慢化 剂、反射层材料 2 课堂教学 8. 材料的 辐照损伤机理、 6 课堂教学
辐照损伤微观结构、性能变化均匀腐蚀、点蚀、晶间腐蚀、9.材料的应力腐蚀、流动腐蚀与防8课堂教学加速腐蚀、氢护机理脆、磨蚀、腐蚀防护机理TeachingMainContentsHoursWhether there is ideological andChapterStylepolitical content1.Material IssuesCombining the developmentLClassroomIntroductionand Challengesteachinghistory of our country's nuclearin Nuclearpowertechnologyfrom laggingbehind to the completelyPower Plantsindependentdevelopment of thelarge advanced pressurized waterreactor'Hualong One',studentsareencouragedto learnfromtheearly domestic nuclear powerleaders. They should aim highwhile also addressing the pressing"bottleneck'issues that the nationcurrentlyfaces2.Properties2Mechanical,ClassroomPhysical, andofMaterialsteachingChemicalProperties ofMaterials23.NuclearClassificationClassroomFuelandteachingMaterialsCharacteristics,*教学大纲In-core(English)Behavior ofSyllabusUO2 Fuel,AccidentTolerant Fuel4. Fuel6ZirconiumClassroomCladdingAlloys andteachingAlloyingMaterialsPrinciples, In-corePerformance ofCladding,AccidentTolerantCladding25.PressureMainClassroomVesselComponents,teachingPerformanceMaterialsRequirements,DissimilarMaterialWelding6.In-core2MaterialClassroomComponentsSelectionteachingCriteria,andEvaporatorFailure
辐照损伤 微观结构、性能 变化 9. 材料的 腐蚀与防 护机理 均匀腐蚀、点 蚀、晶间腐蚀、 应力腐蚀、流动 加速腐蚀、氢 脆、磨蚀、腐蚀 防护机理 8 课堂教学 *教学大纲 (English) Syllabus Chapter Main Contents Hours Teaching Style Whether there is ideological and political content 1. Introduction Material Issues and Challenges in Nuclear Power Plants 2 Classroom teaching Combining the development history of our country's nuclear power technology from lagging behind to the completely independent development of the large advanced pressurized water reactor 'Hualong One', students are encouraged to learn from the early domestic nuclear power leaders. They should aim high while also addressing the pressing 'bottleneck' issues that the nation currently faces. 2. Properties of Materials Mechanical, Physical, and Chemical Properties of Materials 2 Classroom teaching 3. Nuclear Fuel Materials Classification and Characteristics, In-core Behavior of UO2 Fuel, Accident Tolerant Fuel 2 Classroom teaching 4. Fuel Cladding Materials Zirconium Alloys and Alloying Principles, In- core Performance of Cladding, Accident Tolerant Cladding 6 Classroom teaching 5. Pressure Vessel Materials Main Components, Performance Requirements, Dissimilar Material Welding 2 Classroom teaching 6. In-core Components and Evaporator Material Selection Criteria, Failure 2 Classroom teaching
MaterialsBehavior7.ControlCoolant,2ClassroomMaterialsModerator, andteachingReflectorMaterials8.ClassroomMechanismsof2IrradiationIrradiationteachingDamageofDamage,Microstructure,MaterialsPerformanceChanges9.8UniformClassroomMechanismsCorrosion,teachingofMaterialPittingCorrosionCorrosion,andIntergranularProtectionCorrosion,StressCorrosion,Flow-AcceleratedCorrosion,HydrogenEmbrittlement,Erosion,CorrosionProtectionMechanisms本课程主要从出勤率和论文两个维度来考察学生对本课程的掌握程度，学生如果平时出勤率低于80%以及期末论文不合格均被视为未通过本课程的学习。*课程要求（中文）RequirementsThestudents are examined intwodimensionsofattendanceandthesis,iftheusual attendance rateis less than 80% and the final paper is not passed, students are considered to have failed the*课程要求course(English)Requirements《核反应堆材料》，主编：周邦新课程资源(中文)ResourcesNuclearEngineeringMaterials,editedbyBangxinZhou课程资源(English)Resources备注Note
Materials Behavior 7. Control Materials Coolant, Moderator, and Reflector Materials 2 Classroom teaching 8. Irradiation Damage of Materials Mechanisms of Irradiation Damage, Microstructure, Performance Changes 2 Classroom teaching 9. Mechanisms of Material Corrosion and Protection Uniform Corrosion, Pitting Corrosion, Intergranular Corrosion, Stress Corrosion, Flow- Accelerated Corrosion, Hydrogen Embrittlement, Erosion, Corrosion Protection Mechanisms 8 Classroom teaching *课程要求 （中文） Requirements 本课程主要从出勤率和论文两个维度来考察学生对本课程的掌握程度，学生如果平时出勤 率低于 80%以及期末论文不合格均被视为未通过本课程的学习。 *课程要求 （English） Requirements The students are examined in two dimensions of attendance and thesis, if the usual attendance rate is less than 80% and the final paper is not passed, students are considered to have failed the course. 课程资源 （中文） Resources 《核反应堆材料》，主编：周邦新 课程资源 （English） Resources “Nuclear Engineering Materials”, edited by Bangxin Zhou 备注 Note