displaying 4841 - 4850 results in total 5327
Najafi, B.; Joglar, F.; Dreisbach, J.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 1. Main Report.Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA; Science Applications International Corp., Los Altos, CA['NUREG-1824', 'EPRI 1011999', 'Volume 1', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 1; Final Report
May 2007
62 p.Hamins, A.; McGrattan, K. B.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 2. Experimental Uncertainty.National Institute of Standards and Technology, Gaithersburg, MD['NUREG-1824', 'EPRI 1011999', 'Volume 2', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 2; Final Report
May 2007
105 p.Dreisbach, J.; Hill, K.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 3. FDTs.Nuclear Regulatory Commission, Washington, DC['NUREG-1824', 'EPRI 1011999', 'Volume 3', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 3; Final Report
May 2007
118 p.Joglar, F.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 4. Fire-Induced Vulnerability Evaluation (FIVE-Rev1).Electric Power Research Institute, Palo Alto, CA['NUREG-1824', 'EPRI 1011999', 'Volume 4', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 4; Final Report
May 2007
100 p.Peacock, R. D.; Reneke, P. A.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 5. Consolidated Fire Growth and Smoke Transport Model (CFAST).National Institute of Standards and Technology, Gaithersburg, MD['NUREG-1824', 'EPRI 1011999', 'Volume 5', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 5; Final Report
May 2007
206 p.Joglar, F.; Gautier, B.; Gay, L.; Texeraud, J.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 6. MAGIC.Electric Power Research Institute, Palo Alto, CA['NUREG-1824', 'EPRI 1011999', 'Volume 6', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 6; Final Report
May 2007
206 p.McGrattan, K. B.
view article (1.0)Verification and Validation of Selected Fire Models for Nuclear Power Plant Applications. Volume 7. Fire Dynamics Simulator (FDS).National Institute of Standards and Technology, Gaithersburg, MD['NUREG-1824', 'EPRI 1011999', 'Volume 7', 'Final Report']Nuclear Regulatory Commission, Washington, DC; Electric Power Research Institute, Palo Alto, CA, NUREG-1824; EPRI 1011999; Volume 7; Final Report
May 2007
205 p.Brown, N.
view article (1.0)Steelwork Partially Protected From Post-Flashover Fires In Gypsum Plasterboard Lined Compartments.University of Canterbury, Christchurch, New ZealandFire Engineering Research Report 07/3Fire Engineering Research Report 07/3
2007
144 p.Trapp, J.
view article (1.0)Ins and Outs of Pressure-Reducing Valves.Elkhart Brass Mfg. Co., IAPlumbing Engineer, Vol. 35, No. 5, 38,40-42, May 2007Bradish, J. K.
view article (1.0)Destruction of Landmark Hotel Spurs Efforts to Protect Historic Structures. On The Job.Firehouse, Vol. 32, No. 5, 50-56, May 2007