Nuclear Reactor Materials Material Science 7th Sem Syllabus for BE 2017 Regulation Anna Univ (Professional Elective II) detail syllabus for Materials Science And Engineering (Material Science), 2017 regulation is collected from the Anna Univ official website and presented for students of Anna University. The details of the course are: course code (ML8008), Category (PE), Contact Periods/week (3), Teaching hours/week (3), Practical Hours/week (0). The total course credits are given in combined syllabus.
For all other material science 7th sem syllabus for be 2017 regulation anna univ you can visit Material Science 7th Sem syllabus for BE 2017 regulation Anna Univ Subjects. For all other Professional Elective II subjects do refer to Professional Elective II. The detail syllabus for nuclear reactor materials is as follows.
Course Objective:
- Import knowledge about different nuclear materials
- Identify the materials for nuclear reactor and fuel
- Knowledge about nuclear waste and prevention techniques
- Know about irradiation effects in nuclear fuels.
Unit I
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Unit II
Nuclear Reactors
Types of reactors-ordinary water moderated reactors, heavy water cooled and moderated reactors-design, construction and control of nuclear reactors-moderators-coolants-reflectors and structural materials, nuclear power stations in India, comparison of nuclear power plants with thermal power plants
Unit III
Fuels
Ores and beneficiation – Uranium and thorium ores, availability in India, solvent extraction and ore beneficiation. fuels of different types – metallic, alloy and dispersion fuels for research reactors, ceramic (oxide, carbide and nitride) fuels for thermal power reactor and fast reactors.
Fabrication of oxide, mixed-oxide and mixed-carbide fuel for power reactors. Fabrication, characterization and property evaluation of advanced fuel type, processes encountered in fabrication, fuel property evaluation – thermal and physical properties
Unit IV
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Unit V
Irradiation Effects in Nuclear Fuels
Irradiation Examination of Fuels, Irradiation behavior of metallic uranium – irradiation growth, thermal cycling, swelling, adjusted uranium, blistering in uranium rods. Irradiation effects in ceramic oxide and mixed oxide fuels, definition and units of burnup, main causes of fuel element failure in power reactors and remedies to avoid failures. Behavior of fuel under off normal and accident condition, criteria for fuel failure during LOCA: oxidation, deformation, stored energy
Course Outcome:
- Use of the Fuel in Nuclear reactor
- Ability to discuss the Nucleator radiation and the controlling methods.
- Ability to examine the fuels.
Text Books:
- Arora and Domkundwar, “Power plant Engineering”, Dhanpati Rai &Co
- Benedict M and Pigter T.A. “Nuclear Chemical Engineering” Mcgraw Hill 1981
- Combined power plants by J.H.Horlocks by Pergamon press
- L.C. Merrite, “Basic principles of Nuclear science and Reactors” Wiley Eastern 1977.
- P.K.Nag, “Power Plant Engineering” Tata Mcgraw Hill, 2007
References:
- Frost, “Nuclear Fuel Elements: Design Fabrication and Performance”, PERGAMON publications, 1982.
- Gupta C K “Materials in Nuclear Applications” vol.1, CRC publications, 1989.
- Kaufman A R, John Wiley, “Nuclear Reactor Fuel Elements, Metallurgy and Fabrication”, 1962
- Olander D R., “Fundamental Aspects of Nuclear Reactor Fuel Elements” NTIS publication, 1976.
For detail syllabus of all other subjects of BE Material Science, 2017 regulation do visit Material Science 7th Sem syllabus for 2017 Regulation.
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