Modifications to the MELCOR code for application in fusion accident analyses

For the past several years, the Fusion Safety Program at the Idaho National Engineering and Environmental Laboratory (INEEL) has modified the MELCOR code in order to assess safety issues associated with loss-of-cooling accidents (LOCAs) and loss-of-vacuum accidents (LOVAs) in the international therm...

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Bibliographic Details
Published in:	Fusion engineering and design Vol. 51; pp. 555 - 563
Main Authors:	Merrill, B.J, Moore, R.L, Polkinghorne, S.T, Petti, D.A
Format:	Journal Article Conference Proceeding
Language:	English
Published:	Amsterdam Elsevier B.V 01-11-2000 New York, NY Elsevier Science
Subjects:	Accident prevention Applied sciences Controled nuclear fusion plants Energy Energy. Thermal use of fuels Engineering design activity Exact sciences and technology Experimental reactors Installations for energy generation and conversion: thermal and electrical energy International thermonuclear experimental reactor Loss of coolant accidents Loss-of-cooling accidents Loss-of-vacuum accidents MELCOR safety engineering Vacuum technology Loss-of-vacuum accidents International thermonuclear experimental reactor Loss-of-cooling accidents MELCOR Engineering design activity Nuclear safety Tokamak Nuclear fusion reactor LOCA Data analysis Database Computation code Safety Modeling LOVA Heat transfer Nuclear reactor
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