ENU 4144 – Nuclear Power Plant Reactor Systems (3 cr), Required Course, Fall 2008 Description: Codes, standards and criteria (general design, quality assurance, etc.) for nuclear power plants; the structure and functions of the NRC; and the nuclear power plant licensing process. The major components and systems of PWR and BWR nuclear power plants. This is a course wherein the prospective nuclear engineer begins to become familiar with the engineering technology and licensing and regulation of the nuclear power industry. Pre-requisite: ENU 4605 and EML 3100 Text: A course notebook will be made available as extensive class handouts during the semester. References: Nuclear Power Plant Systems and Equipment, by Kenneth C. Lish, Industrial Press, Inc. New York, 1972. Nuclear Reactor Engineering, Chapters 10 and 11, Glasstone and Sesonske, 3rd Edition, Van Nostrand Reinhold Company, 1981. Steam, Its Generation and Use, Babcock and Wilcox Co. Code of Federal Regulations, Chapter 10, U.S. Government Printing Office. ABET Program Educational Objectives / Professional Components Supported by Course: 1. Provide graduates with the knowledge and skills required for successful careers in Nuclear

Engineering and related disciplines for the benefit of society. 2. Provide graduates with the education that enables them to pursue advanced degrees. 4. Provide graduates with the knowledge and skills such that they practice high ethical and

professional standards in the pursuit of successful careers in Nuclear Engineering and related disciplines.

Program Outcomes Supported by Course: Outcome a: an ability to apply knowledge of mathematics, science and engineering for problem solving in engineering. Outcome e: an ability to identify, formulate and solve engineering problems. Outcome f: an understanding of professional, ethical and regulatory responsibility in engineering practice. Outcome g: an ability to communicate effectively, using both oral and written presentations, in engineering practice. Outcome j: a knowledge of contemporary issues as they relate to professional engineering practice. Outcome n: an ability to work professionally in one or more of the areas of: nuclear power reactors, nuclear instrumentation and measurement, radiation protection and shielding and radiation sources and applications. Grading: Homework (Problem Sets): 15%; 1st Exam: 25 %; 2nd Exam: 30 % Final Exam: 30% Homework problems will include basic energy/power calculations related to core fissioning and ancillary calculations, e.g., calculation of associated fission gas release and swelling; basic energy balance equations for primary loop and components, for balance-of-plant loop and components and for selected auxiliary systems and components; basic thermodynamic calculations related to

problems such as pressurizer sizing, pump sizing, etc. and basic thermodynamic calculations related to containment heat load and containment pressure and temperature.

ENU 4144 Nuclear Power Reactor Systems – Course Outline 1. Introduction (3 classes) The Nuclear Industry: Status and Issues Important national and international offices and nuclear organizations including the U.S. DOE and U.S. NRC Introduction to Commercial Nuclear Power Plants – LWRs 2. Regulation (5 classes) Code of Federal Regulations General Design Criteria (10CFR50, App. A) Quality Assurance Criteria (10CFR50, App B) Contents of Applications (PSAR and FSAR) (10CFR50.34) Combined Operating License - COL (10CFR 52) Technical Specifications (10CFR50.36) Reactor Siting Criteria (10CFR100) Codes and Standards and Safety Analysis Reports (SARs) 3. Licensing (3 classes) Licensing Procedures and Documentation Design Certification Documents (DCDs) Licensing Sequence of Events 4. PWR Reactor Systems and Technology (15 classes) Reactor Vessel and Internals Reactor Core and Fuel Reactor Coolant System: coolant pumps, pressurizer and steam generators Thermal Hydraulic Design Limitations Auxiliary Systems: Chemical and Volume Control System, Residual Heat Removal System, ECCS and Fuel Handling System Reactor Control System Reactor Protection System Nuclear and Non-nuclear Instrumentation Systems 5. BWR Reactor Systems and Technology (10 classes) Reactor Vessel and Internals Reactor Core and Fuel Reactor Coolant System (recirculation loop) Thermal Hydraulic Design Limitations Auxiliary Systems Reactor Control System Reactor Protection System Nuclear and Non-nuclear Instrumentation Systems 6. LWR Support Systems and Technology (6 classes) Seismic Design Criteria and Containment Design Containment and Plant Ventilation Systems Component Cooling Systems Spent Fuel Storage Facilities and Rad Waste Disposal Systems There will be guest lectures/seminars on relevant topics by professionals from utilities, vendors and government agencies and tours of power reactor facilities, depending upon availability. Prepared by: Edward T. Dugan