NUCLEAR ENGINEERING & TECHNOLOGY PROGRAM
(Inter-Disciplinary Programme)
PROFESSORS
PROGRAMME COMMITTEE :
Kalra MS
msk
7527
M.S. Kalra (ME)
msk
7527
Munshi P
pmunshi
7243
P. Munshi (ME)
pmunshi
7243
Vyas NS (Head)
vyas
7040
A. Sengupta (ME/NET )
osegu
7035
S. Qureshi (EE)
qureshi
7339
Qureshi S
qureshi
7339
K. Muralidhar
kmurli
7775
osegu
7035
Emeritus Fellow Sengupta A
Convenor, DUGC :
P. Munshi (ME)
pmunshi
7243
Convenor, DPGC :
P. Munshi (ME)
pmunshi
7243
Faculty Counsellor: E-mails :
[email protected]
Tel Nos : +91-512-259 7243
In view of the rapidly expanding nuclear energy programme in India and the growing need for qualified engineers, an inter-disciplinary postgraduate programme in Nuclear Engineering and Technology leading to the M.Tech. and Ph.D. degrees was initiated in July 1974. Admission requirement for the M.Tech. programme is either a Bachelor’s degree in any branch of engineering or a Master ‘s in Physics. Laboratories for research and teaching in Nuclear Engineering include the facilities of the central nuclear physics laboratory, a 5 Curie Pu-Be neutron source, data processing equipment, various types of radiation detecting and counting equipment. Other relevant Institute facilities such as digital computers, material science laboratory and electronics laboratory are also available. Potential areas of research are: Nuclear reactor, transport theory, theory of kinetic equations, plasma physics, safety and controls, computerized tomography, solitons, reliability engineering, two phase flow, radiation physics, radiation detection and instrumentation. The course work consists of a set of required subjects covering the basic concepts of nuclear science and engineering, experimental techniques and a set of electives that may be taken from within or outside of the Programme. A brief description of these courses is given below :
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STRUCTURE OF THE PROGRAM Compulsory Courses
Elective Courses
NT 601
NT 612
NT 602
NT 615
NT 611 NT 621
NT 631 NT 632
NT 614
NT 633
NT 699
NT 634
NT 799
NT 641 NT 642 NT 651 NT 652 NT 698
NT 601 NT 611 NT 614
or (ME 681) Mathematical methods Nuclear Power Engineering I Nuclear Power Engineering II
NT 612 NT 631 NT 633
Reactor Physics Neutron Transport Theory Nuclear Fusion
NT 602 NT 621 NT 699 799 NT 615 NT 632 NT 634
Nuclear and Reactor Physics Nuclear Measurements Lab. Thesis research
Nuclear Power Engineering III Radioisotope Application in Engineering Nuclear Reactions & Interaction of Radiation with Matter NT 641 Introduction to Computerized Tomography NT 642 Nondestructive Evaluation NT 651 Fast Reactor Technology NT 652 Nuclear Fuel Cycle NT 698 Special Topics (Reliability Engineering, Theory of Kinetic Equations, Introduction to Fully Ionized Plasmas) Electives (Outside Department) Numerical Methods for Engineers (ME) Numerical Analysis (Maths) Nuclear Materials (Met) Optimal Control Theory (EE) Nuclear Reactions (Phy) Electronics (Phy)
Students are expected to have an adequate background in Mathematics, Nuclear Physics and Heat Transfer. In order to meet the degree requirements, students will have to take additional courses. The purpose of the additional courses is to gain knowledge in a particular area which will facilitate research work in that area of specialization. Some of these courses are given below :
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NT 612 L-T-P-D-[C] 3-0-0-0-[4]
NT 602 L-T-P-D-[C] 3-0-0-0-[4]
REACTOR PHYSICS Neutron transport equation and its approximate methods of solution: spherical harmonics and discrete ordinates methods. Diffusion equation and criticality studies, numerical criticality search. Energy dependent diffusion equation, multigroup method. Two group analysis, criticality equation, Collapsing of groups. Slowing down equation and its solution by the step-by -step methods exact and approximate. Methods of solution.approximate methods. Variational calculus, Euler-Lagrange equation and Raleigh Ritz method. Optimization methods. Analytic functions, conformal mappings. Cartesian tensors, order, transformation rules, calculus. Nonliear maps, local inverse and implicit function theorem. Bifurcation and Liapunov-Schmidt reduction. NUCLEAR AND REACTOR PHYSICS Introduction to quantum mechanics, Schrodinger equation and its solution by separation of variables. Potential well, quantum states. Nuclear charge, radius and mass. Binding energy. Nuclear forces and the deuteron problem. Semiempirical mass formula. Energetics of nuclear stability. Reaction channels, Compound nucleus. Energy dependence of neutron cross sections and Brecit-wigner formula. The fission process. Neutron diffusion theory showing down length. Critical mass and size. Numerical criticality search. Four-factor formula. Energy dependent diffusion. Multigroup diffusion, group constants and matrix formulation. Two-group analysis. Age theory. Slowing down theory.
NT 611 L-T-P-D-[C] 3-0-0-0-[4]
NT 601 L-T-P-D-[C] 3-0-0-0-[4]
NUCLEAR POWER ENGINEERING I Types of nuclear reactors. Heat generation in fuel elements and temperature distributions. Heat removal, Reactor coolants. Single phase and two phase heat transfer. Boiling and flow regimes. Heat transfer and fluid flow correlations. Pressure drops due to friction and pumping power. Reactor core MATHEMATICAL METHODS Sets, relations, mappings and inverses. Systems of linear equations. Vector space, subspace, basis, null and range space, invertibility and matrix representation. Echelon form, Fredholm Alternative and orthogonalization. Eigenvalues and eigenfunctions. First and second order ODE. Laplace and Fourier methods; series solution and orthogonal polynomials. Sturn Lioville problem. Classification of PDEs. Solution in finite and semi-infinite media. Fredholm and Volterra integral equations. Iterative and thermal hydraulic analysis. Hot spot factors.
374
NT 614 L-T-P-D-[C] 3-0-0-0-[4]
NT 615
NUCLEAR POWER ENGINEERING II
Prereq. NT 611
Introduction to control theory. Point reactor kinetics with introduction to feedback effects. Non-linear effects. Shielding. Introduction to reactor reliability and safety analysis. Radioactive waste disposal. Economics of nuclear power. Introduction to nuclear fuel cycles. NUCLEAR POWER ENGINEERING III Health Physics: introduction, radiation protection, regulatory aspects, radiation biology, operational radiation protection, radiation protection monitoring. Process Instrumentation and Control: basic concepts, sensing and transmission/ receiving of temperature, flow, liquid level, pressure, force, viscousity, humidity. Nuclear Materials: fabrication and properties of zircaloy, metallic fuels, ceramic fuels, applications. Nuclear Chemistry: role of chemistry in nuclear engineering, chemical processes in the nuclear fuel cycle, production of uranium, plutonium, thorium, heavy water, water treatment, corrosion, decontamination.
NT 621 L-T-P-D-[C] 1-0-6-0-[4]
NT 631 L-T-P-D-[C] 3-0-0-0-[4]
NT 632 L-T-P-D-[C] 3-0-0-0-[4]
NUCLEAR MEASUREMENTS LABORATORY Biological effects of radiation; Radiation monitoring; G-M Counter characteristics, counting statistics. Scintillation detectors and gamma spectrometry. Multichannel analysis. Semiconductor detectors for alpha and gamma spectrometry. Coincidence measurements. BF 3 counters. Foil Activation. Cadmium ratio measurements. Neutron diffusion length and age measurements. Experiments using Van de Graaff. Radioisotope applications, Computer simulation studies. NEUTRON TRANSPORT THEORY Neutron transport equation and its derivation. Case’s singular eigen function method for the 1 speed transport equation. Spherical harmonics approximation: diffusion and higher order PN approximations and their relation to Case’s method. TPN and FN approximations. The neutron slowing down equation: its analysis as a differential- difference equation. Exact and approximate solution and their inter-relationship. Energy dependent spatial neutron transport. RADIOISOTOPE APPLICATION IN ENGINEERING Nuclear detectors. Counting statistics. Radiation safety. Radiotracer principles. Flow measurements. Applications in analysis. Process studies. Wear measurements and other production engineering applications. Selected examples of Industrial radiotracer applications.
375
Radiogauging principles, Alpha particle gauges based on transmissions. Scattering and ionization effects. Beta transmission gauges for measurements of sheets thickness, density and composition analysis. X-ray fluorescence principles. Neutron gauges. Well logging. Gamma and neutron radiography. Radioisotope power packs. High level radio-isotope applications including radiation therapy sterilization plants, radiation processing and food irradiation. NT 633 L-T-P-D-[C] 3-0-0-0-[4]
NT 634 L-T-P-D-[C] 3-0-0-0-[4]
NT 641 L-T-P-D-[C] 3-0-0-0-[4]
NT 642 L-T-P-D-[C] 3-0-0-0-[4]
NT 651 L-T-P-D-[C] 3-0-0-0-[4]
NUCLEAR FUSION Basic physics of fusion reactions, thermonuclear cross-sections. Radiation losses: bremsstrahlung and cyclotron radiation. Energy balance: Lawson criterion, neutronnics in a fusion reactor. Plasma confinement: Pinch effect, stellarator and magnetic mirrors. Plasma heating ohmic and adiabatic compression: Tokamaks. Inertial confinement of plasma microexplosion and laser fusion. NUCLEAR REACTION AND INTERACTION OF RADIATION WITH MATTER Introduction of nuclear Properties, Angular momentum and spin, Shell model, Nuclear Reactions, Kinematics, Cross-sections, and decay, Resonances, Energy loss of radiation going through matter, Shielding Concepts Geometries, and shield attenuation calculations. INTRODUCTION TO COMPUTERIZED TOMOGRAPHY Overview, medical imaging, nondestructive testing, radiographic techniques, various applications, data collection, design of CT scanners for materials testing, flow measurement, related instrumentation, Radon’s inversion formula, centralslice theorem, fan-beam inversion, filter functions, convolving functions transform methods, series-expansion methods, convolution algorithms, error estimates, direct theorems, inverse theorems. NON DESTRUCTIVE EVALUATION Introduction, various NDE techniques- ultrasonics, eddy current, magnetic flux leakage, radiography, optical, tomographic extensions of classical NDE/NDT methods Radon inversion, data collection mechanisms, applications in industrial situations. FAST REACTOR TECHNO-LOGY Introduction, Core design, Fuel-element design, Fuel management, Heat transport systems, Steam-generators, IHX design, Sodium pumps & piping, Instrumentation & controls, safety, extractive and physical metallurgy of nuclear materials, Metallic fuels, cladding, post irradiation examination, fabrication of fuel, Steels for nuclear environment, advanced NDT techniques, corrosion. 376
NT 652 L-T-P-D-[C] 3-0-0-0-[4]
Nuclear Fuel Cycle Introduction, nuclear fuels, uranium technology, xirconium process, babrication of fuel assemblies, PWR fuel, mixed-oxide fuel, irradiated fuel, reprocessing, radioactivity, contamination, waste management, enrichment of uranium, thorium cycle, fast reactor fuel cycle and fuel fabrication, environmental impact and safety.
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