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MELCOR
Results: 35

#	Item
1	404 MELCOR Modeling of Fukushima Unit 2 Accident Add to Reading List Source URL: www.nss.si Language: English - Date: 2014-07-21 14:41:30
2	NES Colloquium Wednesday, 04 March 2015, 11::00, OSGA/EG06 Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1 Dr. L. Fernandez, LTH Add to Reading List Source URL: www.psi.ch Language: English - Date: 2015-06-15 03:43:49
3	406 ANALYSIS OF PASSIVE REACTOR CAVITY COOLING SYSTEM FOR A 600 MWTH HTGR USING MELCOR CODE Add to Reading List Source URL: www.nss.si Language: English - Date: 2014-07-21 14:41:29
4	405 Modeling of ESBWR Passive Containment Cooling System with MELCOR Add to Reading List Source URL: www.nss.si Language: English - Date: 2014-07-21 14:41:31
5	404 MELCOR Modeling of Fukushima Unit 2 Accident Add to Reading List Source URL: www.djs.si Language: English - Date: 2014-07-21 14:41:30 Nuclear safety Nuclear energy in the United States Fukushima Prefecture Boiling water reactor Fukushima Daiichi Nuclear Power Plant Nuclear power plant Reactor vessel Boiling water reactor safety systems Fukushima Daiichi nuclear disaster Nuclear technology Energy Nuclear physics
6	405 Modeling of ESBWR Passive Containment Cooling System with MELCOR Add to Reading List Source URL: www.djs.si Language: English - Date: 2014-07-21 14:41:31 Chemical engineering Heat conduction Laboratory glassware Atmospheric thermodynamics Boiling water reactor Surface condenser Condenser Economic Simplified Boiling Water Reactor Heat exchanger Mechanical engineering Thermodynamics Heat transfer
7	Photos placed in horizontal position with even amount of white space between photos and header DOE/NRC Analysis of Fukushima Accident Using MELCOR 2.1 Add to Reading List Source URL: www.nrc.gov Language: English - Date: 2013-07-17 09:55:01 Nuclear safety Boiling water reactor Emerging technologies Nuclear meltdown Nuclear reactor safety systems Hydrogen vehicle Gasket Flange Containment building Nuclear technology Energy Technology
8	MELCOR ACCIDENT ANALYSIS FOR ARIES-ACT Paul W. Humrickhouse, Brad J. Merrill Idaho National Laboratory, PO box 1625 MS 3840, Idaho Falls, ID 83415, We model a loss of flow accident (LOFA) in t Add to Reading List Source URL: www-ferp.ucsd.edu Language: English - Date: 2012-10-09 11:46:23 Nuclear reactors Heat transfer Energy conversion Heat conduction Loss-of-coolant accident Heat exchanger Coolant Fusion power Light water reactor Energy Nuclear technology Nuclear safety
9	MELCOR accident analysis for ARIES-ACT Paul Humrickhouse Brad Merrill INL Fusion Safety Program 20th TOFE Add to Reading List Source URL: www-ferp.ucsd.edu Language: English - Date: 2012-09-18 14:45:00 Nuclear technology Heat conduction Heat transfer Containers Cryostat Heat exchanger Nuclear reactor Energy Technology Energy conversion
10	MELCOR ACCIDENT ANALYSIS FOR ARIES-ACT Paul W. Humrickhouse, Brad J. Merrill Idaho National Laboratory, PO box 1625 MS 3840, Idaho Falls, ID 83415, We model a loss of flow accident (LOFA) in t Add to Reading List Source URL: aries.ucsd.edu Language: English - Date: 2012-10-09 11:46:23 Nuclear reactors Heat transfer Energy conversion Heat conduction Loss-of-coolant accident Heat exchanger Coolant Fusion power Light water reactor Energy Nuclear technology Nuclear safety