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Turbulet flow in a model nuclear fuel rod bundle containing partial flow blockages BNWL-SA-6207 DE95 006509

Turbulet flow in a model nuclear fuel rod bundle containing partial flow blockages BNWL-SA-6207 DE95 006509
Microform規格・テクニカルリポート類
Creer, J. M, Rowe, D. S, Bates, J. M, Sutey, A. M1977<LS-DE95/006509>
National Diet Library

Analysis of In-Pile Heat Transfer Tests (EPRI ; EPRI-NP-4899)

Analysis of In-Pile Heat Transfer Tests (EPRI ; EPRI-NP-4899)
Paper図書
Rowe, D.S./Nielsen, L.H.Electric Power Research Institute(Electric Power Research Institute)1986.
Other Libraries in Japan
  • Author HeadingRowe, D.S. Nielsen, L.H.

DONOR FLOW FORMULATION FOR MOMENTUM FLUX DIFFERENCING (CONF ; CONF-840614-54)

DONOR FLOW FORMULATION FOR MOMENTUM FLUX DIFFERENCING (CONF ; CONF-840614-54)
Paper図書
1984.
Other Libraries in Japan

FUEL PERFORMANCE IMPROVEMENT PROGRAM. QUARTERLY PROGRESS REPORT, APRIL-JUNE 1977. (COO ; COO-4066-1)

FUEL PERFORMANCE IMPROVEMENT PROGRAM. QUARTERLY PROGRESS REPORT, APRIL-JUNE 1977. (COO ; COO-4066-1)
Paper図書
ROWE, D.S.1977.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

Transient thermal-hydraulic experiments: N-Reactor inlet connector break HW-84104 DE94 018252

Transient thermal-hydraulic experiments: N-Reactor inlet connector break HW-84104 DE94 018252
Microform規格・テクニカルリポート類
Rowe, D. S, Anderson, J. K, Thorne, W. L1964<LS-DE94/018252>
National Diet Library

CORE THERMAL MODEL DEVELOPMENT AND EXPERIMENTS. PROGRESS REPORT, 1 JULY 1974-31 DECEMBER 1974. (BNWL ; BNWL-1924-1)

CORE THERMAL MODEL DEVELOPMENT AND EXPERIMENTS. PROGRESS REPORT, 1 JULY 1974-31 DECEMBER 1974. (BNWL ; BNWL-1924-1)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1975.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

SUBCHANNEL CODE DEVELOPMENT AND DATA ANALYSIS. PROGRESS REPORT, JULY 1-DECEMBER 31, 1974. (BNWL ; BNWL-B-390-1)

SUBCHANNEL CODE DEVELOPMENT AND DATA ANALYSIS. PROGRESS REPORT, JULY 1-DECEMBER 31, 1974. (BNWL ; BNWL-B-390-1)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1974.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

EXPERIMENTAL STUDY OF FLOW AND PRESSURE IN ROD BUNDLE SUBCHANNELS CONTAINING BLOCKAGES. (BNWL ; BNWL-1771)

EXPERIMENTAL STUDY OF FLOW AND PRESSURE IN ROD BUNDLE SUBCHANNELS CONTAINING BLOCKAGES. (BNWL ; BNWL-1771)
Paper図書
ROWE, D.S.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1973.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

MEASUREMENT OF TURBULENT VELOCITY, INTENSITY AND SCALE IN ROD BUNDLE FLOW CHANNELS CONTAINING A GRID SPACER. (BNWL ; BNWL-1757)

MEASUREMENT OF TURBULENT VELOCITY, INTENSITY AND SCALE IN ROD BUNDLE FLOW CHANNELS CONTAINING A GRID SPACER. (BNWL ; BNWL-1757)
Paper図書
ROWE, D.S.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1973.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

COBRA IIIC: DIGITAL COMPUTER PROGRAM FOR STEADY STATE AND TRANSIENT THERMAL HYDRAULIC ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-1695)

COBRA IIIC: DIGITAL COMPUTER PROGRAM FOR STEADY STATE AND TRANSIENT THERMAL HYDRAULIC ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-1695)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1973.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

MEASUREMENT OF TURBULENT VELOCITY, INTENSITY AND SCALE IN ROD BUNDLE FLOW CHANNELS. (BNWL ; BNWL-1736)

MEASUREMENT OF TURBULENT VELOCITY, INTENSITY AND SCALE IN ROD BUNDLE FLOW CHANNELS. (BNWL ; BNWL-1736)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1973.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

STUDIES OF A RADIOACTIVE GEL DIFFUSION TECHNIQUE AND ITS APPLICATION TO... (IAEA ; IAEA-R-858-F)

STUDIES OF A RADIOACTIVE GEL DIFFUSION TECHNIQUE AND ITS APPLICATION TO... (IAEA ; IAEA-R-858-F)
Paper図書
ROWE, D.S.International Atomic Energy Agency(International Atomic Energy Agency)1972.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

IMPROVED MATHEMATICAL MODEL FOR TRANSIENT SUBCHANNEL ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-SA-4333)

IMPROVED MATHEMATICAL MODEL FOR TRANSIENT SUBCHANNEL ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-SA-4333)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1972.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

COBRA-3: A DIGITAL COMPUTER PROGRAM FOR STEADY STATE AND TRANSIENT THERMAL-HYDRAULIC ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-B-82)

COBRA-3: A DIGITAL COMPUTER PROGRAM FOR STEADY STATE AND TRANSIENT THERMAL-HYDRAULIC ANALYSIS OF ROD BUNDLE NUCLEAR FUEL ELEMENTS. (BNWL ; BNWL-B-82)
Paper図書
ROWE, D.S.Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1971.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

COBRA-II: a digital computer program for thermal-hydraulic subchannel analysis of rod bundle nuclear fuel elements (BNWL ; BNWL-1229)

COBRA-II: a digital computer program for thermal-hydraulic subchannel analysis of rod bundle nuclear fuel elements (BNWL ; BNWL-1229)
Paper図書
Rowe, D.S.Battelle-Northwest, Pacific Northwest Lab.1970.2.
Other Libraries in Japan
  • Author HeadingRowe, D.S.

Cross flow mixing between parallel flow channels during boiling. Part III. Effect of spacers on mixing between two channels. (BNWL ; BNWL-371(Pt.3))

Cross flow mixing between parallel flow channels during boiling. Part III. Effect of spacers on mixing between two channels. (BNWL ; BNWL-371(Pt.3))
Paper図書
Rowe, D.S., Angle, C.W.Battelle-Northwest, Pacific Northwest Lab.1969.1.
Other Libraries in Japan
  • Author HeadingRowe, D.S. Angle, C.W.

A study of hydraulic and nuclear stability of boiling water parallel flow channel reactor systems (BNWL ; BNWL-574)

A study of hydraulic and nuclear stability of boiling water parallel flow channel reactor systems (BNWL ; BNWL-574)
Paper図書
Worden, J.R., Rowe, D.S., Dionne, P.J.Battelle-Northwest, Pacific Northwest Lab.1968.2.
Other Libraries in Japan
  • Author HeadingWorden, J.R. Rowe, D.S. Dionne, P.J.

DIGITAL PROGRAM FOR THE PREDICTION AND ANALYSIS OF ONE-DIMENSIONAL, TWO-PHASE FLOW TRANSIENTS FOLLOWING SUDDEN LOSS OF COOLANT OR LOSS OF PRESSURE. (BNWL ; BNWL-CC-1495)

DIGITAL PROGRAM FOR THE PREDICTION AND ANALYSIS OF ONE-DIMENSIONAL, TWO-PHASE FLOW TRANSIENTS FOLLOWING SUDDEN LOSS OF COOLANT OR LOSS OF PRESSURE. (BNWL ; BNWL-CC-1495)
Paper図書
ROWE, D.S.(et al.)Battelle Pacific Northwest Laboratories(Battelle Pacific Northwest Laboratories)1967.
Other Libraries in Japan
  • Author HeadingROWE, D.S.

Crossflow mixing between parallel flow channels during boiling. Part II. Measurement of flow and enthalpy in two parallel channels (BNWL ; BNWL-371(Pt.2))

Crossflow mixing between parallel flow channels during boiling. Part II. Measurement of flow and enthalpy in two parallel channels (BNWL ; BNWL-371(Pt.2))
Paper図書
Rowe, D.S., Angle, C.W.Battelle-Northwest, Pacific Northwest Lab.1967.12.
Other Libraries in Japan
  • Author HeadingRowe, D.S. Angle, C.W.

Cross-flow mixing between parallel flow channels during boiling. Part I. COBRA: Computer program for coolant boiling in rod arrays (BNWL ; BNWL-371(Pt.1))

Cross-flow mixing between parallel flow channels during boiling. Part I. COBRA: Computer program for coolant boiling in rod arrays (BNWL ; BNWL-371(Pt.1))
Paper図書
Rowe, D.S.Battelle-Northwest, Pacific Northwest Lab.1967.3.
Other Libraries in Japan
  • Author HeadingRowe, D.S.
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