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Progress in Accident Analysis of the HYLIFE-II Inertial Fusion Energy Power Plant Design.

DE200415006138

Publication Date	2000
Personal Author	Reyes, S.; Latkowski, J. F.; Gomez del Rio, J.; Sanz, J.
Page Count	12
Abstract	The present work continues our effort to perform an integrated safety analysis for the HYLIFE-I1 inertial fusion energy (IFE) power plant design. Recently we developed a base case for a severe accident scenario in order to calculate accident doses for HYLIFE-11. It consisted of a total loss of coolant accident (LOCA) in which all the liquid flibe was lost at the beginning of the accident. Results showed that the off-site dose was below the limit given by the DOE Fusion Safety Standards for public protection in case of accident, and That this dose was dominated by the tritium released during the accident.
Keywords	HYLIFE converter Thermonuclear power plants Design Safety Accident analysis Accident prevention Tritium Analyses Public safety Radioactivity Computer programs Inertial fusion energy (IFE) Loss of coolant accident (LOCA) Loss of flow accident (LOFA) DOE Fusion Safety Standards Liquid flibe MELCOR thermal-hydraulics code
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Lawrence Livermore National Lab., CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200414

Progress in Accident Analysis of the HYLIFE-II Inertial Fusion Energy Power Plant Design.

Progress in Accident Analysis of the HYLIFE-II Inertial Fusion Energy Power Plant Design.
DE200415006138

Publication Date	2000
Personal Author	Reyes, S.; Latkowski, J. F.; Gomez del Rio, J.; Sanz, J.
Page Count	12
Abstract	The present work continues our effort to perform an integrated safety analysis for the HYLIFE-I1 inertial fusion energy (IFE) power plant design. Recently we developed a base case for a severe accident scenario in order to calculate accident doses for HYLIFE-11. It consisted of a total loss of coolant accident (LOCA) in which all the liquid flibe was lost at the beginning of the accident. Results showed that the off-site dose was below the limit given by the DOE Fusion Safety Standards for public protection in case of accident, and That this dose was dominated by the tritium released during the accident.
Keywords	HYLIFE converter Thermonuclear power plants Design Safety Accident analysis Accident prevention Tritium Analyses Public safety Radioactivity Computer programs Inertial fusion energy (IFE) Loss of coolant accident (LOCA) Loss of flow accident (LOFA) DOE Fusion Safety Standards Liquid flibe MELCOR thermal-hydraulics code
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Lawrence Livermore National Lab., CA.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200414