Nuclear Power Engineering Secondary cooling circuit is a must in molten sodium cooled fast breeder reactor for Avoiding the mixing of water with radioactive sodium, as it may cause explosion Lowering the coolant circulation pressure Faster heat removal rate from the core Achieving high degree of superheat in the steam Avoiding the mixing of water with radioactive sodium, as it may cause explosion Lowering the coolant circulation pressure Faster heat removal rate from the core Achieving high degree of superheat in the steam ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Plutonium Is recovered from spent fuel from thermal nuclear reactor Neither A nor B Both A & B Has much lower melting point (640°C ) compared to thorium (1690°C) Is recovered from spent fuel from thermal nuclear reactor Neither A nor B Both A & B Has much lower melting point (640°C ) compared to thorium (1690°C) ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Which of the following is not a good moderating material? Concrete All of these Boron 18/8 stainless steel Concrete All of these Boron 18/8 stainless steel ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Which of the following is the best nuclear fuel? U-234 Np- 239 Pu-239 Th-236 U-234 Np- 239 Pu-239 Th-236 ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Coolant used in a fast breeder reactor is Heavy water Helium Molten sodium Ordinary water Heavy water Helium Molten sodium Ordinary water ANSWER DOWNLOAD EXAMIANS APP
Nuclear Power Engineering Bhabha Atomic Research Centre (BARC) located at Trombay (near Bombay) has A very large capacity (100 tons/yr) heavy water plant All of these A 420 MW nuclear power plant Five operating research reactors (namely Apsara, Cirus Zerelina, Purnima and Dhurva) A very large capacity (100 tons/yr) heavy water plant All of these A 420 MW nuclear power plant Five operating research reactors (namely Apsara, Cirus Zerelina, Purnima and Dhurva) ANSWER DOWNLOAD EXAMIANS APP
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