A demonstration experiment of steam-driven, high-pressure melt ejection

• Main Authors: Allen, M.D., Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)), Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA))
• Other Authors: U.S. Nuclear Regulatory Commission
• Format: Report
• Language: English
• Published: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research 1990
• Subjects: Heat Transfer; Bwr Type Reactors; Reactor Accidents; Hydraulics; Chemical Reaction Kinetics; Oxides; 22 General Studies Of Nuclear Reactors; Computer Codes; Demonstration Programs; 21 Specific Nuclear Reactors And Associated Plants; Fluid Mechanics; Chalcogenides; Transition Element Compounds; Water Cooled Reactors; Kinetics; Simulation; Containment; Structural Models; Accidents; Iron Oxides; Safety; Reactors; Temperature Measurement; Test Facilities; Mechanics; Reactor Safety; 210200 > Power Reactors; Nonbreeding; Light-Water Moderated; Nonboiling Water Cooled; Pwr Type Reactors; Blowdown; Energy Transfer; Elements; Meltdown; Hydrogen; Oxygen Compounds; Corium; 210100 > Power Reactors; Boiling Water Cooled; Reaction Kinetics; Pressure Measurement; Iron Compounds; Scale Models; Nonmetals; Water Moderated Reactors 220900* > Nuclear Reactor Technology > Reactor Safety; Steam; C Codes; Surtsey
• Online Access: https://doi.org/10.2172/6978726; https://digital.library.unt.edu/ark:/67531/metadc1190882/

A steam blowdown test was performed at the Surtsey Direct Heating Test Facility to test the steam supply system and burst diaphragm arrangement that will be used in subsequent Surtsey Direct Containment Heating (DCH) experiments. Following successful completion of the steam blowdown test, the HIPS-1...