Principal Research Results Development of multi-COBRA: A Transient Thermal-hydraulic Analysis Code for Fast Reactor Cores Background In liquid-metal-cooled fast reactors (LMFRs), the coolant flow coastdown events due to - Liquid metal cooled reactor - Document - PDFSEARCH.IO

First Page	Meta Content
	Principal Research Results Development of multi-COBRA: A Transient Thermal-hydraulic Analysis Code for Fast Reactor Cores Background In liquid-metal-cooled fast reactors (LMFRs), the coolant flow coastdown events due to Add to Reading List Document Date: 2008-09-29 03:25:43 Open Document File Size: 86,89 KB Share Result on Facebook Country United States / / IndustryTerm metal fuel fast reactor cores / energy / / Organization Assembly-2 Assembly / Assembly-N Assembly / / Person Hirokazu Ohta / Takeshi Yokoo / / Position driver / Research Scientist / Senior Research Scientist / / Technology heat transfer / / SocialTag Nuclear accidents Nuclear safety Experimental Breeder Reactor II Liquid metal cooled reactor Experimental Breeder Reactor I Nuclear fuel Breeder reactor Heat transfer Boiling water reactor Nuclear technology

Principal Research Results Development of multi-COBRA: A Transient Thermal-hydraulic Analysis Code for Fast Reactor Cores Background In liquid-metal-cooled fast reactors (LMFRs), the coolant flow coastdown events due toAdd to Reading List