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Vibration and wear in steam generator tubes following chemical cleaning. Final report. (NUREG ; NUREG/CR-4276; PNL-5477-VOL.2)

Vibration and wear in steam generator tubes following chemical cleaning. Final report. (NUREG ; NUREG/CR-4276; PNL-5477-VOL.2)
Paper図書
Enderlin, W.I./Fitzsimmons, D.E.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingEnderlin, W.I. Fitzsimmons, D.E.

Electrically Heated Ex-Reactor Pellet-Cladding Interaction (PC1) Simulations Utilizing Irradiated Zircaloy Cladding (NUREG ; NUREG/CR-3999; PNL-5245)

Electrically Heated Ex-Reactor Pellet-Cladding Interaction (PC1) Simulations Utilizing Irradiated Zircaloy Cladding (NUREG ; NUREG/CR-3999; PNL-5245)
Paper図書
Barner, J.O./Fitzsimmons, D.E.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1985.
Other Libraries in Japan
  • Author HeadingBarner, J.O. Fitzsimmons, D.E.

Critical heat flux & two phase hydraulic investigation of a 16-rod simulation of a BWR fuel assembly BNWL-SA-3724 DE95 006510

Critical heat flux & two phase hydraulic investigation of a 16-rod simulation of a BWR fuel assembly BNWL-SA-3724 DE95 006510
Microform規格・テクニカルリポート類
Sutey, A. M, Fitzsimmons, D. E, Thorne, W. L, Torobin, L. B1971<LS-DE95/006510>
National Diet Library

Steady state thermal hydraulic characteristics of one-inch overbore fuel BNWL-CC-2581 DE94 018018

Steady state thermal hydraulic characteristics of one-inch overbore fuel BNWL-CC-2581 DE94 018018
Microform規格・テクニカルリポート類
Sutey, A. M, Fitzsimmons, D. E, Angle, C. W1970<LS-DE94/018018>
National Diet Library

Experimental determination of the departure from nucleate boiling in large rod bundles at high pressure experimental equipment and experimental operation BNWL-CC-1095 DE95 006511

Experimental determination of the departure from nucleate boiling in large rod bundles at high pressure experimental equipment and experimental operation BNWL-CC-1095 DE95 006511
Microform規格・テクニカルリポート類
Fitzsimmons, D. E, Thorne, W. L, Batch, J. M1967<LS-DE95/006511>
National Diet Library

Effects of interjunction flow on thermal and hydraulic characteristics of an N-Reactor fuel column BNWL-CC-193 DE94 018007

Effects of interjunction flow on thermal and hydraulic characteristics of an N-Reactor fuel column BNWL-CC-193 DE94 018007
Microform規格・テクニカルリポート類
Anderson, J. K, Batch, J. M, Thorne, W. L, Fitzsimmons, D. E1965<LS-DE94/018007>
National Diet Library

Hydraulic demand curves for BDF geometry with enlarged outlet fittings: 25 PSIG rear header pressure HW-64398-1 DE94 017218

Hydraulic demand curves for BDF geometry with enlarged outlet fittings: 25 PSIG rear header pressure HW-64398-1 DE94 017218
Microform規格・テクニカルリポート類
Waters, E. D, Fitzsimmons, D. E1961<LS-DE94/017218>
National Diet Library

Pressure required to overcome boiling at low tube powers: BDF reactors HW-66274 DE94 010525

Pressure required to overcome boiling at low tube powers: BDF reactors HW-66274 DE94 010525
Microform規格・テクニカルリポート類
Waters, E. D, Fitzsimmons, D. E1960<LS-DE94/010525>
National Diet Library

Report on preliminary laboratory experiments investigating consequences of failure of front hydraulic fittings in K reactor geometry HW-61849 DE94 016395

Report on preliminary laboratory experiments investigating consequences of failure of front hydraulic fittings in K reactor geometry HW-61849 DE94 016395
Microform規格・テクニカルリポート類
Hesson, G. M, Fitzsimmons, D. E1959<LS-DE94/016395>
National Diet Library

K Reactor panellit protection against plugging incidents with low front header pressure HW-60518 DE94 016394

K Reactor panellit protection against plugging incidents with low front header pressure HW-60518 DE94 016394
Microform規格・テクニカルリポート類
Fitzsimmons, D. E, Hesson, G. M1959<LS-DE94/016394>
National Diet Library

Interim report on laboratory experiments investigating consequences of failure of front hydraulic fittings in 'C' OCD geometry. Progress rept HW-60287 DE94 016655

Interim report on laboratory experiments investigating consequences of failure of front hydraulic fittings in 'C' OCD geometry. Progress rept HW-60287 DE94 016655
Microform規格・テクニカルリポート類
Fitzsimmons, D. E, Hesson, G. M1959<LS-DE94/016655>
National Diet Library

Preliminary results of the loss-of-coolant heat transfer study for N- Reactor (BNWL ; BNWL-B-88)

Preliminary results of the loss-of-coolant heat transfer study for N- Reactor (BNWL ; BNWL-B-88)
Paper図書
Sutey, A.M., Fitzsimmons, D.E., Collingham, R.E.Battelle Pacific Northwest Labs.1971.5.
Other Libraries in Japan
  • Author HeadingSutey, A.M. Fitzsimmons, D.E. Collingham, R.E.

Experimental boiling burnout heat fluxes with an electrically heated 19-rod bundle test section (BNWL ; BNWL-206)

Experimental boiling burnout heat fluxes with an electrically heated 19-rod bundle test section (BNWL ; BNWL-206)
Paper図書
Hesson, G.M., Fitzsimmons, D.E., Batch, J.M.Battelle-Northwest, Pacific Northwest Lab.1965.12.
Other Libraries in Japan
  • Author HeadingHesson, G.M. Fitzsimmons, D.E. Batch, J.M.

Two-phase pressure drop in piping components (HW ; HW-80970(Rev.1))

Two-phase pressure drop in piping components (HW ; HW-80970(Rev.1))
Paper図書
Fitzsimmons, D.E.Hanford Atomic Products Operation1964.3.20.
Other Libraries in Japan
  • Author HeadingFitzsimmons, D.E.

Boiling burnout experiments with fog-cooled nineteen-rod bundle test sections (HW ; HW-80523(Rev.1))

Boiling burnout experiments with fog-cooled nineteen-rod bundle test sections (HW ; HW-80523(Rev.1))
Paper図書
Hesson, G.M., Fitzsimmons, D.E., Batch, J.M.Hanford Atomic Products Operation1964.3.
Other Libraries in Japan
  • Author HeadingHesson, G.M. Fitzsimmons, D.E. Batch, J.M.

Comparison of boiling burnout data for 19-rod bundles in horizontal and vertical positions (HW ; HW-83443(Rev.1))

Comparison of boiling burnout data for 19-rod bundles in horizontal and vertical positions (HW ; HW-83443(Rev.1))
Paper図書
G.M. Hesson, D.E. Fitzsimmons, J.M. BatchHanford Atomic Products Operation1964.7.
Other Libraries in Japan
  • Author HeadingHesson, G.M. Fitzsimmons, D.E. Batch, J.M.

Boiling burnout experiments with 19-rod bundles in axial flow (HW ; HW-77303)

Boiling burnout experiments with 19-rod bundles in axial flow (HW ; HW-77303)
Paper図書
Waters, E.D. [et al.]Hanford Atomic Products Operation1963.8.
Other Libraries in Japan
  • Author HeadingWaters, E.D. Hesson, G.M. Fitzsimmons, D.E. Batch, J.M.

PRELIMINARY BOILING BURNOUT EXPERIMENTS WITH A 19-ROD BUNDLE GEOMETRY IN AXIAL FLOW (HW ; HW-73395)

PRELIMINARY BOILING BURNOUT EXPERIMENTS WITH A 19-ROD BUNDLE GEOMETRY IN AXIAL FLOW (HW ; HW-73395)
Paper図書
1962.
Other Libraries in Japan

Preliminary boiling burnout experiments with a 19-rod bundle geometry in axial flow (HW ; HW-73395)

Preliminary boiling burnout experiments with a 19-rod bundle geometry in axial flow (HW ; HW-73395)
Paper図書
Hesson, G.M. [et al.]General Electric Co. Hanford Atomic Products Operation1962.
Other Libraries in Japan
  • Author HeadingHesson, G.M. Fitzsimmons, D.E. Waters, E.D. Batch, J.M.

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