-
2
-
-
33846904876
-
Application and visualization capability of the sub-channel code F-COBRA-TF
-
Nuremberg, Germany, May 10-12
-
Glück M., and Kollmann T. Application and visualization capability of the sub-channel code F-COBRA-TF. Annual Meeting of Nuclear Technology. Nuremberg, Germany, May 10-12 (2005)
-
(2005)
Annual Meeting of Nuclear Technology
-
-
Glück, M.1
Kollmann, T.2
-
3
-
-
33846931444
-
A new individual film model in the sub-channel code F-COBRA-TF
-
Aachen, Germany, May 16-18
-
Glück M. A new individual film model in the sub-channel code F-COBRA-TF. Annual Meeting of Nuclear Technology. Aachen, Germany, May 16-18 (2006)
-
(2006)
Annual Meeting of Nuclear Technology
-
-
Glück, M.1
-
5
-
-
33846934312
-
-
Herkenrath, H., et al. 1981. Experimental investigation of the enthalpy and mass flow distribution in 16-rod cluster with BWR, PWR - Geometries and conditions. Final Report. EUR 7575 EN, Joint Research Center Ispra, Italy.
-
-
-
-
7
-
-
33846919728
-
-
Janssen, E., 1971. Two-phase flow and heat transfer in multi-rod geometries - Final Report. GEAP-10347 AEC Research and Development Report.
-
-
-
-
8
-
-
33846903429
-
-
Kemner, H., 1984. Coolant mixture in spacer grids without mixing vanes. Internal Report of Kraftwerk Union (KWU), Erlangen, Germany (not public available, in German).
-
-
-
-
9
-
-
33846932649
-
KATHY: FRAMATOME ANP's thermal hydraulic test loop
-
Nara, Japan, October 4-8
-
Kreuter D., Wich M., Imbert P., and Pruitt D. KATHY: FRAMATOME ANP's thermal hydraulic test loop. The Sixth International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6). Nara, Japan, October 4-8 (2004)
-
(2004)
The Sixth International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6)
-
-
Kreuter, D.1
Wich, M.2
Imbert, P.3
Pruitt, D.4
-
10
-
-
33846896525
-
-
Lahey, R.T., et al., 1970. Two-phase flow and heat transfer in multi-rod geometries: sub-channel and pressure drop measurements in nine-rod bundle for diabatic and adiabatic conditions. GEAP-13049 AEC Research and Development Report.
-
-
-
-
12
-
-
0021428916
-
Flow regime transition criteria for upward two-phase flow in vertical tubes
-
Mishima K., and Ishii M. Flow regime transition criteria for upward two-phase flow in vertical tubes. Int. J. Heat Mass Transfer 27 5 (1984) 723-737
-
(1984)
Int. J. Heat Mass Transfer
, vol.27
, Issue.5
, pp. 723-737
-
-
Mishima, K.1
Ishii, M.2
-
13
-
-
0020496777
-
Evaluation of turbulent mixing parameter in nuclear fuel rod bundles
-
Honolulu, Hawaii, March 20-24
-
Reddy D.G., and Fighetti C.F. Evaluation of turbulent mixing parameter in nuclear fuel rod bundles. Proceedings of ASME JSME Thermal Engineering Joint Conference, vol. 3. Honolulu, Hawaii, March 20-24 (1983) 411-415
-
(1983)
Proceedings of ASME JSME Thermal Engineering Joint Conference, vol. 3
, pp. 411-415
-
-
Reddy, D.G.1
Fighetti, C.F.2
-
14
-
-
85069350956
-
Turbulent interchange mixing in rod bundles and the role of secondary flows
-
San Francisco
-
Rogers J.T., and Tahir A.E.E. Turbulent interchange mixing in rod bundles and the role of secondary flows. ASME, Heat Transfer Conference. San Francisco (1975)
-
(1975)
ASME, Heat Transfer Conference
-
-
Rogers, J.T.1
Tahir, A.E.E.2
-
15
-
-
33846926639
-
3D computational fluid dynamic analyses of flow in sub-channels under swirl conditions
-
Nuremberg, Germany, May 10-12
-
Salnikova T. 3D computational fluid dynamic analyses of flow in sub-channels under swirl conditions. Annual Meeting of Nuclear Technology. Nuremberg, Germany, May 10-12 (2005)
-
(2005)
Annual Meeting of Nuclear Technology
-
-
Salnikova, T.1
-
16
-
-
33846913564
-
The OECD/NRC BWR full-size fine-mesh bundle tests benchmark (BFBT) - General description
-
Nara, Japan, October 4-8
-
Sartori E., Hochreiter L., Ivanov K., and Utsuno H. The OECD/NRC BWR full-size fine-mesh bundle tests benchmark (BFBT) - General description. Proceedings of NUTHOS-6 Conference. Nara, Japan, October 4-8 (2004)
-
(2004)
Proceedings of NUTHOS-6 Conference
-
-
Sartori, E.1
Hochreiter, L.2
Ivanov, K.3
Utsuno, H.4
-
17
-
-
0018967113
-
Modeling flow pattern transitions for steady upward gas-liquid flow in vertical tubes
-
Taitel Y., Bornea D., and Dukler A.E. Modeling flow pattern transitions for steady upward gas-liquid flow in vertical tubes. AIChE J. 26 3 (1980) 345-354
-
(1980)
AIChE J.
, vol.26
, Issue.3
, pp. 345-354
-
-
Taitel, Y.1
Bornea, D.2
Dukler, A.E.3
-
18
-
-
0003599718
-
-
Pacific Northwest Laboratory, Richland, WA NUREG/CR-3046, PNL-4385
-
Thurgood M.J., et al. COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems vol. 1-5 (1983), Pacific Northwest Laboratory, Richland, WA NUREG/CR-3046, PNL-4385
-
(1983)
COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems
, vol.1-5
-
-
Thurgood, M.J.1
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