Improving Accident Tolerance of Nuclear Fuel with Coated Mo-alloy Cladding

Article English OPEN
Bo Cheng; Young-Jin Kim; Peter Chou;
  • Publisher: Elsevier
  • Journal: Nuclear Engineering and Technology,volume 48,issue 1,pages16-25 (issn: 1738-5733)
  • Related identifiers: doi: 10.1016/
  • Subject: Nuclear engineering. Atomic power | Nuclear Energy and Engineering | TK9001-9401

In severe loss of coolant accidents (LOCA), similar to those experienced at Fukushima Daiichi and Three Mile Island Unit 1, the zirconium alloy fuel cladding materials are rapidly heated due to nuclear decay heating and rapid exothermic oxidation of zirconium with steam... View more
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