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FY 1995 progress report on the ANS thermal-hydraulic test loop operation and results ORNLTM12972 DE98 003622

FY 1995 progress report on the ANS thermal-hydraulic test loop operation and results ORNLTM12972 DE98 003622
マイクロ規格・テクニカルリポート類
Siman-Tov, M, Felde, D. K, Farquharson, G, McDuffee, J. L, McFee, M. T1997<LS-DE98/003622>
国立国会図書館

Thermal analysis of two-phase microchannel cooling CONF-961105-5 DE96 010728

Thermal analysis of two-phase microchannel cooling CONF-961105-5 DE96 010728
紙マイクロ規格・テクニカルリポート類
Chen, N. C. J, Felde, D. K, Yoder, G. L1996<LS-DE96/010728>
国立国会図書館全国の図書館

Flow blockage analysis for the advanced neutron source reactor ORNL-6860 DE96 006229

Flow blockage analysis for the advanced neutron source reactor ORNL-6860 DE96 006229
マイクロ規格・テクニカルリポート類
Stovall, T. K, Crabtree, J. A, Felde, D. K, Park, J. E1996<LS-DE96/006229>
国立国会図書館

Experimental study of static flow instability in subcooled flow boiling in parallel channels CONF-9501130-1 DE96 008649

Experimental study of static flow instability in subcooled flow boiling in parallel channels CONF-9501130-1 DE96 008649
紙マイクロ規格・テクニカルリポート類
Siman-Tov, M, Felde, D. K, McDuffee, J. L, Yoder, G. L1995<LS-DE96/008649>
国立国会図書館全国の図書館

Influence of coolant pH on corrosion of 6061 aluminum under reactor heat transfer conditions ORNL/TM-13083 DE96 006223

Influence of coolant pH on corrosion of 6061 aluminum under reactor heat transfer conditions ORNL/TM-13083 DE96 006223
マイクロ規格・テクニカルリポート類
Pawel, S. J, Felde, D. K, Pawel, R. E1995<LS-DE96/006223>
国立国会図書館

Static-flow-instability in subcooled flow boiling in wide rectangular parallel channels CONF-950445-1 DE94 019324

Static-flow-instability in subcooled flow boiling in wide rectangular parallel channels CONF-950445-1 DE94 019324
紙マイクロ規格・テクニカルリポート類
Siman-Tov, M, Felde, D. K, McDuffee, J. L, Yoder, G. L1995<LS-DE94/019324>
国立国会図書館全国の図書館

Static flow instability in subcooled flow boiling in parallel channels CONF-950445-2 DE95 009122

Static flow instability in subcooled flow boiling in parallel channels CONF-950445-2 DE95 009122
紙マイクロ規格・テクニカルリポート類
Siman-Tov, M, Felde, D. K, McDuffee, J. L, Yoder, G. L1995<LS-DE95/009122>
国立国会図書館全国の図書館

FY 1993 progress report on the ANS thermal-hydraulic test loop operation and results ORNL/M-3789 DE95 002303

FY 1993 progress report on the ANS thermal-hydraulic test loop operation and results ORNL/M-3789 DE95 002303
マイクロ規格・テクニカルリポート類
Siman-Tov, M, Felde, D. K, Farquharson, G1994<LS-DE95/002303>
国立国会図書館

ADVANCED NEUTRON SOURCE REACTOR THERMAL-HYDRAULIC TEST LOOP FACILITY DESCRIPTION. (ORNL ; ORNL/TM-12397)

ADVANCED NEUTRON SOURCE REACTOR THERMAL-HYDRAULIC TEST LOOP FACILITY DESCRIPTION. (ORNL ; ORNL/TM-12397)
紙図書
FELDE, D.K.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1994.
全国の図書館
  • 著者標目FELDE, D.K.

EXPERIMENTAL INVESTIGATION OF THERMAL LIMITS IN PARALLEL PLATE CONFIGURATION FOR THE ADVANCED NEUTRON SOURCE REACTOR (CONF ; CONF-930830-6)

EXPERIMENTAL INVESTIGATION OF THERMAL LIMITS IN PARALLEL PLATE CONFIGURATION FOR THE ADVANCED NEUTRON SOURCE REACTOR (CONF ; CONF-930830-6)
紙図書
SIMAN-TOV, M.// FELDE, D.K.// KAMINAGA, M.// YODER, G.L. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
全国の図書館
  • 著者標目SIMAN-TOV, M. FELDE, D.K. KAMINAGA, M. YODER, G.L.

ADVANCED NEUTRON SOURCE THERMAL HYDRAULIC TEST LOOP (CONF ; CONF-920538-11)

ADVANCED NEUTRON SOURCE THERMAL HYDRAULIC TEST LOOP (CONF ; CONF-920538-11)
紙図書
FELDE, D.K.// MONTGOMERY, B.H.// YODER, G.L.// SKRZYCKE, D.P. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1992.
全国の図書館
  • 著者標目FELDE, D.K. MONTGOMERY, B.H. YODER, G.L. ...

FACILITY DESCRIPTION. THTF MOD 3 ORNL PWR BDHT SEPARATE-EFFECTS PROGRAM. (NUREG ; NUREG-CR-2640)

FACILITY DESCRIPTION. THTF MOD 3 ORNL PWR BDHT SEPARATE-EFFECTS PROGRAM. (NUREG ; NUREG-CR-2640)
紙図書
FELDE, D.K.(et al.)NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
全国の図書館
  • 著者標目FELDE, D.K.

ORNL Rod Bundle Heat Transfer Test Data Volume 1. ORNL Small Break LOCA Test Series 1; Experimental Data Report (NUREG ; NUREG/CR-2525-V.1; ORNL/NUREG/TM-407/V1)

ORNL Rod Bundle Heat Transfer Test Data Volume 1. ORNL Small Break LOCA Test Series 1; Experimental Data Report (NUREG ; NUREG/CR-2525-V.1; ORNL/NUREG/TM-407/V1)
紙図書
Anklam, T.M./Felde, D.K.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1982.
全国の図書館
  • 著者標目Anklam, T.M. Felde, D.K.

SIMULATION OF HEAT AND MASS TRANSFER PROCESSES IN MOLTEN CORE DEBRIS-CONCRETE SYSTEMS. (COO ; COO-4261-11)

SIMULATION OF HEAT AND MASS TRANSFER PROCESSES IN MOLTEN CORE DEBRIS-CONCRETE SYSTEMS. (COO ; COO-4261-11)
紙図書
FELDE, D.K.(et al.)1979.
全国の図書館
  • 著者標目FELDE, D.K.

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for July-September 1979 (NUREG ; NUREG/CR-1121) (ORNL ; ORNL/NUREG/TM-363)

Quarterly Progress Report on Blowdown Heat Transfer Separate-Effects Program for July-September 1979 (NUREG ; NUREG/CR-1121) (ORNL ; ORNL/NUREG/TM-363)
紙図書
J.D. White [et al.]Oak Ridge National Lab.1979.12.
全国の図書館
  • 著者標目...Craddick, W.G. Felde, D.K. Flanders, R.M. Hagar, R.C. Ot...

CONVECTIVE HEAT TRANSFER CORRELATIONS FOR MOLTEN CORE DEBRISPOOLS GROWING IN CONCRETE. (COO ; COO-4261-8)

CONVECTIVE HEAT TRANSFER CORRELATIONS FOR MOLTEN CORE DEBRISPOOLS GROWING IN CONCRETE. (COO ; COO-4261-8)
紙図書
FELDE, D.K.(et al.)
全国の図書館
  • 著者標目FELDE, D.K.

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