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Research Paper | Mechanical Engineering | India | Volume 4 Issue 11, November 2015

Prediction of Field Flow and Temperature Profile in Calandria Vessel

Ankul Pratap Singh | Dr. M. D. Nadar

Abstract: Nuclear power generator consists of nuclear reactor, steam generator, heavy water turbine, condenser, and hot well pump. Nuclear reactor generates steam at high-pressure 70 bar to 100 bar and temperature range 400 K to 525 K. It consists of heavy water which acts as moderator. The moderator has fluid properties of velocity, viscosity, density, temperature, pressure etc. Moderator is a medium that reduces the speed of fast neutrons, turning them into thermal neutrons capable of sustaining a nuclear chain reaction. Due to this, moderator gets heated and removes heat from nuclear reactor core. The problems faced in nuclear reactor are as follows, nuclear chain reaction is happening in the core of the reactor. During chain reaction, core emits neutrons and large amount of atomic energy. The generated atomic energy converts coolant and heavy water into steam with high pressure and temperature. The high pressure and high temperature of generated steam may lead to burst the nuclear reactor. This paper includes identifying the technical parameters, which are involved in the nuclear reactor chain reactions. The technical parameter intensities are to be measured and are need to take necessary safety precautionary measurements to protect abnormal accidents in the nuclear reactor. Technical process parameters of generated steam like pressure, temperature, energy and velocities etc. are been considered in this investigation for safety precautionary measures. This paper gives a relation amongst temperature, pressure, velocity and energy, mathematical model is used to predict the temperature and velocity at particular instant and position of fluids.

Keywords: Prediction of field flow, Temperature Profile, Calandria Vessel, Pressure profile, Fluent

Edition: Volume 4 Issue 11, November 2015,

Pages: 997 - 1001

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