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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

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
  • Author HeadingPadilla, A Jr Rowe, D S

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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
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