This course, designed for first-semester freshmen, reviews and discusses the history of energy use by the world, the relation between energy usage and quality of life, the social impact of energy use, and the environmental constraints on energy usage. In particular, the role that engineering disciplines play in solving energy problems will be discussed. The full impact that the various energy alternatives have on economic and environmental issues will be reviewed in order to provide a rational basis for energy choices for the future. Typically offered Fall.

NUCL 11000 Introduction To Energy Engineering

Introduction To Energy Engineering

In this course, the student performs a small independent project in nuclear engineering under direct faculty supervision.

NUCL 12000 Freshman Research Project

Freshman Research Project

A course designed to acquaint students with the field of nuclear engineering and design. Concepts of fission, fusion, radioactivity, and neutron physics are introduced. Modern applications of nuclear technology, including nuclear medicine, food preservation, space reactors and propulsion.

NUCL 20000 Introduction to Nuclear Engineering

Introduction to Nuclear Engineering

A laboratory course designed for the study of the properties of radiation, radioactive material, and radiation detectors. The hazards of radiation and safe handling techniques are emphasized.

NUCL 20500 Nuclear Engineering Undergraduate Laboratory I

Nuclear Engineering Undergraduate Laboratory I

Analysis of stress and strain; equations of equilibrium and compatibility; stress-strain laws; extension, torsion, and bending of bars; membrane theory of pressure vessels; combined loading conditions; transformation of stresses and principal stresses; elastic stability, elected topics.

NUCL 27300 Mechanics Of Materials

Mechanics Of Materials

Professional experience in nuclear engineering. Program coordinated by school with cooperation of participating employers. Students submit summary report and company evaluation. Professional Practice students only. Permission of department required.

NUCL 29199 Cooperative Experience I

Cooperative Experience I

NUCL 29299 Cooperative Experience II

Cooperative Experience II

Career areas in nuclear engineering, job opportunities, areas of related study, topics of current interest, orientation, professional ethics, and responsibility.

NUCL 29800 Sophomore Seminar

Sophomore Seminar

Review of atomic properties and introduction to nuclear models. Discussion of radioactive decay and the interaction of nuclear radiation and reaction products with matter. Energetics and cross-sections of nuclear reactions with applications to problems typical of nuclear engineering.

NUCL 30000 Nuclear Structure And Radiation Interactions

Nuclear Structure And Radiation Interactions

Continuation of NUCL 20500. Experiments with scintillation detectors, multichannel analyzers, neutron detectors, the subcritical pile, and the reactor will be performed. Measurements will be made to demonstrate neutron activation analysis techniques, neutron slowing down, neutron flux distributions, and the effects of control rods on neutron fluxes.

NUCL 30500 Nuclear Engineering Undergraduate Laboratory II

Nuclear Engineering Undergraduate Laboratory II

Development of diffusion theory for neutrons. Neutron interactions and development of one-group neutron diffusion theory with point, plane, and fission sources. Application to one- and two-region reactors. Introduction to buckling, multiplication constants, critical size, neutron slowing down, and resonance capture. Applications using two-group theory.

NUCL 31000 Introduction To Neutron Physics

Introduction To Neutron Physics

Nuclear environments and materials selection for nuclear applications, bonding, crystal structure and symmetry, defects and irradiation, chemical thermodynamics, phase equilibria, phase transformations, and corrosion in nuclear systems and design.

NUCL 32000 Introduction To Materials For Nuclear Applications

Introduction To Materials For Nuclear Applications

Nuclear materials laboratory that evaluates various characterization techniques and technologies, tensile properties, hardness, fracture toughness, microstructures, X-ray diffraction, electron microscopy, mechanical properties of thin-films, NDE techniques and data acquisition in materials characterization techniques.

NUCL 32500 Nuclear Materials Laboratory

Nuclear Materials Laboratory

The first of an integrated two-course sequence introducing the concepts of nuclear reactor thermal transport and associated hydraulics with applications to design and safety. Macroscopic balances, dimensional analysis, and flow measurement. Fluid behavior, momentum transfer, and applications to reactor systems and design.

NUCL 35000 Nuclear Thermal-Hydraulics I

Nuclear Thermal-Hydraulics I

Emphasis is given to the fluid transport of heat from reactor fuel elements. Heat transfer in fluids, analogies, and applications to reactor coolant channel analysis. Two-phase flow and convective boiling. Radiative heat transfer. Applications to safety analysis and reactor design.

NUCL 35100 Nuclear Thermal-Hydraulics II

Nuclear Thermal-Hydraulics II

Laboratory course corresponding to NUCL 35000 and NUCL 35100.  Various fluid flow and heat transfer phenomena applied to nuclear reactor systems and design.

NUCL 35500 Nuclear Thermohydraulics Laboratory

Nuclear Thermohydraulics Laboratory

To obtain professional practice with qualified employers within industry, government, or small business. Professional Practice students only. Permission of department required.

NUCL 38199 Professional Practice Co-Op I

Professional Practice Co-Op I

NUCL 38299 Professional Practice Co-Op II

Professional Practice Co-Op II

NUCL 38399 Professional Practice Co-Op III

Professional Practice Co-Op III

NUCL 39399 Cooperative Experience III

Cooperative Experience III

NUCL 39499 Extensive Cooperative Experience IV

Extensive Cooperative Experience IV

NUCL 39599 Extensive Cooperative Experience V

Extensive Cooperative Experience V

To obtain professional practice with qualified employers within industry, government, or small business. Permission of department required.

NUCL 39699 Professional Practice Internship

Professional Practice Internship

NUCL 39800 Junior Seminar

Junior Seminar

Principles and practice of power plant systems with design applications; thermal cycles, heat transport, mechanical designs, control, safety analysis, shielding analysis, fuel cycles; resources, optimization, options, waste management. Fusion and alternate energy sources.

NUCL 40200 Engineering Of Nuclear Power Systems

Engineering Of Nuclear Power Systems

Intermediate treatment of reactor theory and its relevance to routine design engineering calculations, including introduction to transport theory, criticality evaluation, multi-group theory, isotopic depletion, and concludes with short overview of multi-level reactor design calculations, critical experiments, and treatment of neutronic uncertainties. List of Topics: Derivation of Boltzmann transport equation, and its reduction to steady state and time dependent diffusion equation. Introduction to multi-group theory, and evaluation of group parameters in both wide and narrow resonance approximations. Introduction to homogenization theory, and evaluation of lattice parameters. Evaluation of criticality condition for bare and reflected reactor geometries. Development of discretization techniques for the time-dependent multi-group diffusion theory equation. Reactor kinetics, reactivity coefficients and reactivity balance equation. Flowchart of multi-level reactor design calculations. Introduction to critical experiments and startup reactor physics test. Sources and treatment of uncertainties in reactor calculations.

NUCL 41000 Introduction To Reactor Theory And Applications

Introduction To Reactor Theory And Applications

Fundamental of radiation interaction with materials and applications, types of radiation and radiation sources, physical mechanisms of radiation interaction with solids, radiation damage, ion mixing, applications in nuclear fission and fusion reactors, applications in materials synthesis.

NUCL 42001 Radiation Interaction With Materials And Applications

Radiation Interaction With Materials And Applications

The course outcome is the writing and presentation of a proposal for the senior design project, NUCL 45000. The tasks include the selection of project design topics (various nuclear engineering components and systems designs), the selection of teams, introduction to design process, team management, communication, and engineering ethics, literature and patents survey, initiation of design activities and familiarization with design tools (for example software).

NUCL 44900 Senior Design Proposal

Senior Design Proposal

Application of the design process to the project design topics identified in NUCL 44900. The design process usually includes, but not limited to, mathematical modeling in design, neutronic, thermal-hydraulics and safety studies, risk assessment, economics, policy and regulation, environmental impact.

NUCL 45000 Design In Nuclear Engineering

Design In Nuclear Engineering

Energy resources and the potential role of nuclear fusion. Ignition and breakeven conditions for fusion power plants. Particle and energy confinement in linear and toroidal magnetic fields. Review of magnetic and inertial confinement experiments and conceptual reactor configurations.

NUCL 46000 Introduction To Controlled Thermonuclear Fusion

Introduction To Controlled Thermonuclear Fusion

The principles of electromechanical energy conversion for a single fuel cell, fuel cell stack, process engineering in the fuel and oxidizer supply systems. Principles, components, operation and performance for alkaline, phosphoric acid, solid polymer, molten carbonate and solid oxide fuel cells. Provides broad insight into science, technology, system design, and safety concerns in design and operation of fuel cells.

NUCL 47000 Fuel Cell Engineering

Fuel Cell Engineering

This course makes students aware of the importance of communication skills-written, oral, graphical and interpersonal-in a successful nuclear engineering career and gives them the opportunity to develop and practice those skills. Students will learn how to access, evaluate, use and synthesize relevant technical literature. In addition, through the writing and speaking assignments, students develop team work skills, gain an understanding of professional and ethical responsibilities of engineering, learn to write a simple propose and learn about selected contemporary global economic, social and political issues, particularly with respect to nuclear topics.  Typically offered  Fall.

NUCL 48000 Nuclear Engineering Technical Communications

Nuclear Engineering Technical Communications

Projects or research of contemporary importance or special interest. Interested students seek a faculty advisor in their area of special interest and together prepare a brief description of the work to be undertaken. May be taken for 1-6 credits in Fall, Spring, or Summer. May be repeated as many times as desired, but only 6 credits may be counted for the technical elective requirement. Permission of instructor required.

NUCL 49000 Independent Study In Nuclear Engineering

Independent Study In Nuclear Engineering

Topics vary. Permission of instructor required.

NUCL 49700 Selected Topics In Nuclear Engineering

Selected Topics In Nuclear Engineering

Topics vary. Permission of instructor required. Typically offered Fall Spring Summer.

NUCL 49700 Intro To Nuclear Reactor Phys

Intro To Nuclear Reactor Phys

NUCL 49700 Intro To Computational Physics

Intro To Computational Physics

NUCL 49700 Sim Nucl Reactor Phys

Sim Nucl Reactor Phys

Lectures to acquaint the senior students with professional ethics, job opportunities, graduate schools, continuing study, and services of professional societies.

NUCL 49800 Senior Seminar

Senior Seminar

A first course for graduate students desiring a nuclear engineering sequence and an elective for students in science or engineering. The course is structured in four parts: (1) Nuclear structure and radiation, biological effects and medical applications of radiation. (2) Basics of neutron and reactor physics, neutron diffusion and reactor criticality. (3) Nuclear materials and waste. (4) Reactor systems and safety.

NUCL 50100 Nuclear Engineering Principles

Nuclear Engineering Principles

Engineering aspects of nuclear power. Materials of construction; fuel and fuel cycles; heat removal; radiation shielding; economics; and nuclear power systems. Permission of instructor required.

NUCL 50200 Nuclear Engineering Systems

Nuclear Engineering Systems

A laboratory course that, when coupled with NUCL 50100, produces a sequence that contains both the theoretical and engineering aspects of nuclear engineering. Topics include radiation detection and analysis, neutronics, and nuclear reactor experiments.

NUCL 50400 Nuclear Engineering Experiments

Nuclear Engineering Experiments

Methodologies of neutron flux calculations, diffusion and slowing down theory, flux separation, material buckling, resonance absorption, Doppler effect, 2-group and multi-group theories, and reactivity balances for design and operation. Introduction to reactor kinetics, delayed neutrons, point reactor kinetics, transient behavior, load changes, reactivity feedback, and safety implications.

NUCL 51000 Nuclear Reactor Theory I

Nuclear Reactor Theory I

Advanced methodologies for neutron flux calculation, nodal methods, introduction to transport theory, transport correction, multigroup theory, and introduction to the generation of group constants. Reactor kinetics, perturbation theory, adjoint fluxes, reactivity calculation from perturbation theory, reactivity coefficients due to Doppler effect, temperature and density changes, void coefficient, and energy and power coefficients. Microkinetics, theory of reactivity measurements, approximate methods: prompt jump approximation, and prompt kinetics. Transients with feedback, safety implications, and spatial kinetics.

NUCL 51100 Reactor Theory And Kinetics

Reactor Theory And Kinetics

Introduction to radiation effects in solids and a survey of nuclear reactor materials. Radiation interaction mechanisms and effects on properties. Reactor material characteristics, selection criteria, testing, and economic considerations.

NUCL 52000 Radiation Effects And Reactor Materials

Radiation Effects And Reactor Materials

Formulations for analyzing complicated thermal-hydraulic phenomena in energy systems. Derivation of two-phase flow field equations and constitutive relations. Thermal-hydraulic modeling of nuclear reactor systems. Analyses of nuclear reactor safety related phenomena based on conservation principles.

NUCL 55100 Mass, Momentum, And Energy Transfer In Energy Systems

Mass, Momentum, And Energy Transfer In Energy Systems

Applications of thermal-sciences to nuclear reactor safety design and risk assessment. Emphasis on illustrating the use of basic principles in quantitative safety assessments of practical and current interest. The basic topics revolve around multiphase transients and applications which include study of accident analysis and its applications to licensing for light water reactor systems and for liquid metal fast breeder reactor.

NUCL 55200 Thermal-Hydraulics And Reactor Safety

Thermal-Hydraulics And Reactor Safety

Introduction of the principles of nuclear science and engineering for addressing industrial and scientific issues ranging from sub-nano-to-macro scales. Areas to be covered include: propulsion, high-energy density materials, supercooling, medical applications, sonoluminescence, novel detection systems for special nuclear and contraband materials, and advanced nuclear fusion power systems.

NUCL 55300 Nano-Macro Scale Applications Of Nuclear Technology

Nano-Macro Scale Applications Of Nuclear Technology

Introduction to electricity and magnetism, magneto-fluid-mechanics and plasma physics. Thermonuclear reactions, power balances, macroscopic and microscopic instabilities. Principles of operation and conceptual design of Tokamaks, Mirror, Theta-Pinch, and Laser-Driven fusion reactors.

NUCL 56000 Introduction To Fusion Technology

Introduction To Fusion Technology

Review of energy sources and study of the basic processes of direct energy conversion and their applications to energy utilization, based on both conventional and nuclear energy conversion schemes. Conventional schemes include thermoelectric, photovoltaic, thermionic, magnetohydrodynamic generators, fuel cell systems, etc.; and nuclear energy conversion schemes correspond to nuclear radiation and fusion energy conversion. Permission of instructor required.

NUCL 56300 Direct Energy Conversion

Direct Energy Conversion

Presentation of the mathematical fundamentals of fuzzy logic theory and a survey of engineering applications. Fuzzy sets; the extension principle; fuzzy numbers; fuzzy relations and composition; linguistic descriptions; implication operators and fuzzy algorithms are formally developed. Applications emphasize the engineering utilization of approximate reasoning to diagnostics, control, safety, and decision-making problems.

NUCL 57000 Fuzzy Approaches In Engineering

Fuzzy Approaches In Engineering

Mathematical fundamentals of computing with neural networks. Survey of engineering applications. Computational metaphors from biological neurons. Artificial neural networks modeling of complex, nonlinear and ill-posed problems. Emphasizes engineering utilization of neural computing to diagnostics, control, safety, and decision-making problems.

NUCL 57500 Neural Computing In Engineering

Neural Computing In Engineering

Independent study projects. Interested students seek a faculty instructor in their area of special interest and prepare a brief description of the independent project to be undertaken. May be taken for 1-6 credits in Fall, Spring, or Summer. May be repeated as many times as desired, but only a maximum of 6 credits may be counted for the degree program requirement. Permission of instructor required.

NUCL 59000 Independent Study In Nuclear Engineering I

Independent Study In Nuclear Engineering I

Development of individual research and study projects. Permission of instructor required.

NUCL 59700 Introduction To Bioelectrics

Introduction To Bioelectrics

Development of individual research and study projects. Permission of instructor required. Typically offered Fall Spring.

NUCL 59700 Big Data & Machine Learn Engr

Big Data & Machine Learn Engr

NUCL 59700 Nuclear Security Systems

Nuclear Security Systems

NUCL 59700 Manuf & Mater For Nuclear

Manuf & Mater For Nuclear

NUCL 59700 Engr Math Using Mathematica

Engr Math Using Mathematica

NUCL 59700 Beam Target Interactions

Beam Target Interactions

NUCL 59700 Nuclear Power&Nonproliferation

Nuclear Power&Nonproliferation

This course covers advanced reactor physics topics including the neutron transport theory, slowing down and resonance escape, and generalized perturbation theory. The neutron transport theory is the fundamental theory describing the neutron flux behaviors in nuclear systems. The slowing down and resonance escape calculations are essential for generating the multi-group cross sections required in the whole-core neutron transport calculations. The generalized perturbation theory is a powerful method for determining the changes in response parameters due to the variations in nuclide densities and microscopic cross sections. Prerequisites: NUCL 51000 and advanced engineering mathematics covering complex analysis, partial differential equations, and integral equations.

NUCL 61000 Nuclear Reactor Theory II

Nuclear Reactor Theory II

Materials phenomena unique to nuclear reactor environments are examined quantitatively. The relation between these phenomena and the structure and properties of engineering materials is discussed. Coupled phenomena are considered in relation to materials modeling codes.  Prerequisite:  NUCL 42000 and NUCL 52000 (or other related/similar courses). Typically offered Spring.

NUCL 62000 Advanced Topics In Radiation Damage

Advanced Topics In Radiation Damage

Safety philosophy, levels and goals of safety. Approaches used for nuclear reactor safety for the protection of public health. Design basis accidents. Engineered safeguards and inherent safety features. Fundamentals of safety related thermal-hydraulic phenomena and their integration into a methodology for containment assessment.  Prerequisite: ME 50500. Typically offered Spring.

NUCL 65000 Thermal Hydraulics For Nuclear Reactor Safety

Thermal Hydraulics For Nuclear Reactor Safety

The course guides the student to two-fluid model solutions using computational fluid dynamics (CFD). Topics include: review of the two-fluid model, review of elliptic and parabolic partial differential equations, description of numerical algorithms, and two-phase flow channel and jet flows. Prerequisite: NUCL 55100 or ME 50600.

NUCL 65500 Two-Phase Flow Computational Fluid Dynamics Applications

Two-Phase Flow Computational Fluid Dynamics Applications

Applications of plasma physics for analysis and design of plasma configurations in fusion reactors. Topics include beam-driven fusion systems, plasma heating and ignition via neutral beams and RF wave heating, plasma waves, kinetic and fluid descriptions of plasmas, and energy transport; blanket neutronics for tritium breeding, energy conversion, and reactor design considerations. Prerequisite: NUCL 56000.

NUCL 66000 Magnetic Confinement Fusion

Magnetic Confinement Fusion

Inertially confined thermonuclear fusion reactions and energy gains; laser-plasma interactions; hydrodynamic compression; energy transports including electron thermal conduction and radiation transport; beam transport and instabilities; driver energy deposition and the driver development for lasers, particle beams and accelerators; and target designs. Approval of Instructor required. Prerequisite: NUCL 56000 or equivalent.

NUCL 66100 Inertial Confinement Fusion Technology

Inertial Confinement Fusion Technology

Discussion by graduate students and invited speakers of their research projects and topics of interest in nuclear engineering.  Prerequisite: Master's student standing and Nuclear Engineering majors only.

NUCL 69600 Nuclear Engineering Seminar

Nuclear Engineering Seminar

Courses on topics of contemporary importance or special interest in nuclear engineering. Hours and credits to be arranged. Permission of instructor required.

NUCL Courses

BoilerClassesis an unofficial catalog for Purdue courses made by Purdue students,
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NUCL Courses

.css-1o363pe{width:var(--chakra-sizes-4);height:var(--chakra-sizes-4);}BoilerClassesis an unofficial catalog for Purdue courses made by Purdue students, based in West Lafayette, Indiana. We'd love to hear your feedback!

BoilerClassesis an unofficial catalog for Purdue courses made by Purdue students,
based in West Lafayette, Indiana. We'd love to hear your feedback!