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Report on Failure Modes in Reactor Pressure Vessel -Incomplete

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Failure Mode and Effect Analysis (FMEA) of Reactor Pressure vessel of PWR
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    Report on possible hazards due to failure of the reactor pressure vessel of a pressurized water reactor Thesis submitted in the fulfilment of the requirements for the award of the degree of MASTER OF TECHNOLOGY (HONS.) IN INDUSTRIAL ENGINEERING BY B.Venkata Sainath Roll No: 10MF3IM05 Under the guidance of Prof. J.Maiti DEPARTMENT OF INDUSTRIAL & SYSTEMS ENGINEEERING INDIAN INSTITUTE OF TECHNOLOGY KHARAGPUR    Table of Contents 1. Introduction:-  ...................................................................................................................................... 4 2. Reactor pressure vessel:-  ..................................................................................................................... 5 2.1. Reactor vessel body:-  ................................................................................................................... 5 2.2. Reactor core:-  ............................................................................................................................... 7 2.3. Coolant/moderator:-  ................................................................................................................... 11 3. Failure Mode and Effect Analysis (FMEA) of Reactor Pressure vessel of PWR   ........................... 14 3.1 Reactor pressure vessel (System ) breakdown using hardware approach (bottom-up approach) ........................................................................................................................................... 14 3.2. Failure modes of the components of Reactor pressure vessel  .................................................... 15  Table of figures Figure 1Cutaway View of Reactor Vessel ................................................................................................ 6 Figure 2 PWR fuel assembly with control rods ....................................................................................... 8 Figure 3 Nuclear fission reaction of Uranium-235 ............................................................................... 12 Figure 4 Breakdown of reactor pressure vessel into components ....................................................... 14    1. Introduction:- Since the demonstration of a sustained fission reactor in 1942, nuclear  power has emerged as a proven technology and as a method for producing electricity in the world. Because of the world’s continuously improving living standards, increased population and concern over the increased concentration of ‘greenhouse gas’ emissions caused by burning fossil fuels, it is not surprising that there is likely to be an increasing demand for nuclear power. About 5.7% of the world’s energy and 13% of the world’s electricity in 2012 was generated from the nuclear power plants (excluding the contribution from naval nuclear fission reactors) [1] .Since power plants are very complex systems ,consisting of many sub-systems and thousands of components, operation and maintenance of them is a challenging task. Sometimes, failure of a single component may lead to the failure of the subsystem which can drastically affect the operation of the plant. One of the most important components in a nuclear power plant is the reactor pressure vessel where the nuclear fission reaction takes place and heat is generated. The present study aims at identification of different failure modes of the reactor pressure vessel and possible hazards due to its failure.
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