Analysis for failure of pressurized tube in the nuclear reactor

A nuclear power plant consists of a reactor core where a nuclear chain reaction continuously produces heat. This heat is utilized to produce steam. The steam drives a turbo-generator to produce electricity. In the advanced heavy water reactor (AHWR) heavy water is used as both moderator and coolant. The CANada Deuterium Uranium (CANDU) concept is the most advanced one in AHWRs. In AHWR power unit consist a heater rod bundle which is surrounded by the pressure tube. A loss of reactor coolant situation can occur due to any rupture of the primary heat transport system. The seriousness of the accident is dependent on the size of the rupture and the reactor shut down (or trip) is based on the system pressure in case of (loss-of-coolant accident) LOCA. The large breaks bring down the reactor system pressure quickly to shutdown the reactor. The book depicts the analysis of the above nuclear reactor heater rods and their analysis in detailed fashion, so that its outcome can be utilized for better propagation of heat and its conservation. This book aids to help researchers, to get a glimpse of thermal energy interaction and safe removal of decay heat.

Autorentext

J'ai obtenu un diplôme en génie mécanique, un master de M.A.N.I.T, Bhopal et un doctorat de N.I.T, Raipur. Je travaille actuellement comme professeur adjoint à l'Université Amity, Gwalior (M.P.). J'ai publié/présenté un grand nombre d'articles techniques dans différents domaines de l'ingénierie mécanique. Mon expérience d'enseignement et de recherche s'étend sur plus de 8 ans.