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Keywords: reflood
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Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 981-990, May 17–21, 2010
Paper No: ICONE18-30030
... 1 Copyright © 2010 by ASME Proceedings of the 18th International Conference on Nuclear Engineering ICONE18 May 17-21, 2010, Xi an, China ICONE18-30030 REFLOOD OXIDATION MODEL BASED ON REACTION-DIFFUSION EQUATIONS Xiaoqiang He, Hongxing Yu, Guangming Jiang National Key Laboratory of Science...
Proceedings Papers

Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 93-103, July 12–16, 2009
Paper No: ICONE17-75101
... 23 02 2010 A series of experimental tests to simulate a reflood phase of a cold-leg LBLOCA of the APR1400 have been performed by using the ATLAS facility. This paper describes related experimental results with respect to the thermal-hydraulic behavior in the core and the system-core...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 123-129, April 14–18, 2002
Paper No: ICONE10-22137
... accidents, quench, reflood, LWR, safety. TION of an uncovered, overheated Light Water Reactor e by water is the main accident management terminating a severe accident transient. But, before cceeds in cooling the fuel elements, the injected nder certain circumstances, trigger an enhanced the Zircaloy...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 967-974, April 14–18, 2002
Paper No: ICONE10-22744
... nozzles, which are located bove the cold leg centre-line. It is expected that this afety design feature greatly enhances the reliability of ergency core cooling (ECC) system. ever, during the LBLOCA reflood phase, the thermal lic phenomena in the DVI downcomer are largely 40~50% of the injected ECC water...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 819-828, April 25–29, 2004
Paper No: ICONE12-49517
... 25 11 2008 The QUENCH program, performed at Forschungszentrum Karlsruhe, Germany, is dedicated to out-of-pile studies of the initiation and progression of damage during core reflood of a degraded commercial nuclear reactor. Main work in this program is spent on the investigation...
Proceedings Papers

Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 415-422, July 17–20, 2006
Paper No: ICONE14-89403
... 17 09 2008 A series of bottom reflood tests were carried out to investigate thermal-hydraulic characteristics during the reflood phase. This paper includes descriptions of three related groups of reflood tests categorized by the geometry of a flow channel and an electric power shape...