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Course Detail

Course Name Nuclear Reactor Thermal-Hydraulics and Safety
Course Code 25TF655
Program M. Tech. in Thermal & Fluids Engineering(Augmented with Artificial Intelligence and Machine Learning)  * for Regular & Working Professionals
Credits 3
Campus Amritapuri

Syllabus

Module 1

Basic concepts of reactor physics, radioactivity. Neutron Scattering. Thermal and fast reactors. Overview of nuclear reactor systems. Sources and distribution of thermal loads in nuclear power reactors.
Flow Regimes in Two-Phase Flow, Two-phase flow models: Homogeneous Equilibrium Model, Separated and Slip Flow Model, Void Fraction Correlations, Stratified Flow Analysis and Flow Pattern transition, Pool Boiling & Flow Boiling Heat Transfer, Critical Flow, Nuclear Applications of Fluid Mechanics and Heat Transfer.

Module 2

Heat generation in fuel, coolant, structural and shield materials and decay heat, Nuclear Heat Transport, steady and unsteady conduction in fuel, cladding, and structural materials elements, Multi-dimensional thermal-hydraulics in plenum.
Hydraulics of reactor system loops, Hydraulics of heated channels.
Thermal stratification, thermalshock, thermalfatigue, gasentrainment,steam-liquiddropletseparation.
Safety philosophy, Thermal Design Principles, Single Channel Analysis, Sub-channel analysis, LOCA and LOFA Modelling, modelling of containment loading. Waste management. Indian nuclear power program.

Module 3

Nuclear Instrumentation, Health Physics, Radiation Shielding.
Review of Thermal-Hydraulics Codes Used for Reactor Accident Analysis, Advanced Safety Concepts and Upcoming Reactor Safety Methods and next generation reactors.
Thermal-Hydraulics Uncertainty Analysis, Probabilistic safety assessment, regulatory procedure and licensing.

Course Outcomes

  • CO1: Application of reactor physics concepts and working of thermal and fast reactors
  • CO2 : Understanding of two-phase flows, boiling, condensation, Critical Heat Flux CO3 : Heat generation and transport in reactor
  • CO4 : Thermal hydraulic phenomena inside reactor vessel and components
  • CO5 : Safety principles & safety evaluation and Licencing aspects
  • CO6 : Analysis of Transient and Accidents

Textbooks/References

  • Todreas, Neil E.,and Mujid S.Kazimi. Nuclear Systems Volume1: Thermal Hydraulic Fundamentals.2nd CRC Press, 2011.
  • Glasstone,S. and Sesonske,A., Nuclear Reactor Engineering, 4thVol.1(2001)Vol.2(2004),CBS Publishers & Distributors
  • , Nuclear Reactor Engineering (Principles and Concepts),S Chand & Company,2013.
  • Lamarsh,J.R. and Baratta, A.J., Introduction to Nuclear Engineering, 3rd Edn, Prentice Hall,2001.
  • Lewis E.E., Nuclear reactor Safety, Wiley Interscience,1977.
  • Tong L.S. and Tang Y.S., Boiling heat transfer and Two-phase Flow, Taylor and Francis,1997.

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