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Evaluation of the nuclear-power-plant operator-licensing examination. Final report (ORNL/TM ; ORNL/TM-8895)

Evaluation of the nuclear-power-plant operator-licensing examination. Final report (ORNL/TM ; ORNL/TM-8895)
Paper図書
Oak Ridge National Lab., TN (USA)(Oak Ridge National Lab., TN (USA))1983.
Other Libraries in Japan
  • Author HeadingFullerton, A.M. Liebowitz, S.J. Morrison, G.W. Peelle, E. Reed, J.H.

Revised uranium-plutonium cycle PWR and BWR models for the ORIGEN computer code (ORNL ; ORNL/TM-6051)

Revised uranium-plutonium cycle PWR and BWR models for the ORIGEN computer code (ORNL ; ORNL/TM-6051)
Paper図書
A.G. Croff [et al.]Oak Ridge National Lab.1978.9.
Other Libraries in Japan
  • Author HeadingCroff, A.G. Bjerke, M.A. Morrison, G.W. Petrie, L.M.

NEW APPROACH TO SAFEGUARDS ACCOUNTIG (ORNL ; ORNL-CSD-TM-25)

NEW APPROACH TO SAFEGUARDS ACCOUNTIG (ORNL ; ORNL-CSD-TM-25)
Paper図書
Pike, D.H./Morrison, G.W.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1977.
Other Libraries in Japan
  • Author HeadingPike, D.H. Morrison, G.W.

PMS1: A FORTRAN MONTE CARLO CODE FOR CORRECTING EXPERIMENTAL FAST-NEUTRON POLARIZATION DATA. (CTC ; CTC-9)

PMS1: A FORTRAN MONTE CARLO CODE FOR CORRECTING EXPERIMENTAL FAST-NEUTRON POLARIZATION DATA. (CTC ; CTC-9)
Paper図書
MORRISON, G.W.(et al.)1969.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

ADJOINT MONTE CARLO CALCULATIONS FOR ENRICHED URANIUM METAL ASSEMBLIES. (K ; K-DP-1637)

ADJOINT MONTE CARLO CALCULATIONS FOR ENRICHED URANIUM METAL ASSEMBLIES. (K ; K-DP-1637)
Paper図書
MORRISON, G.W.(et al.)1966.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

REACTOR AND CONVRG FORTRAN SUBROUTINES FOR DETERMINING SOURCE CONVERGENCE FOR THE 05R MONTE-CARLO NEUTRON TRANSPORT CODE. (ORNL ; ORNL-TM-1325)

REACTOR AND CONVRG FORTRAN SUBROUTINES FOR DETERMINING SOURCE CONVERGENCE FOR THE 05R MONTE-CARLO NEUTRON TRANSPORT CODE. (ORNL ; ORNL-TM-1325)
Paper図書
MORRISON, G.W.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

ACTIVT: AN 05R MONTE CARLO ANALYSIS ROUTINE FOR CALCULATION OF ACTIVATION. (ORNL ; ORNL-TM-1674)

ACTIVT: AN 05R MONTE CARLO ANALYSIS ROUTINE FOR CALCULATION OF ACTIVATION. (ORNL ; ORNL-TM-1674)
Paper図書
MORRISON, G.W.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

SPCTRM - AN 05R MONTE CARLO ANALYSIS ROUTINE FOR CALCULATING THE NEUTRON ENERGY SPECTRUM. (ORNL ; ORNL-TM-1245)

SPCTRM - AN 05R MONTE CARLO ANALYSIS ROUTINE FOR CALCULATING THE NEUTRON ENERGY SPECTRUM. (ORNL ; ORNL-TM-1245)
Paper図書
MORRISON, G.W.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1965.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

PROMPT NEUTRON DECAY CONSTANTS CALCULATED IN HIGHLY ENRICHED URANIUM METAL ASSEMBLIES. (K ; K-DP-2251)

PROMPT NEUTRON DECAY CONSTANTS CALCULATED IN HIGHLY ENRICHED URANIUM METAL ASSEMBLIES. (K ; K-DP-2251)
Paper図書
MORRISON, G.W.(et al.)
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING CRITICALITY PROBLEMS OF SPENT FUEL CASKS. (CONF ; CONF-720607-9)

USE OF THE MORSE MONTE CARLO CODE TO SOLVE SHIELDING CRITICALITY PROBLEMS OF SPENT FUEL CASKS. (CONF ; CONF-720607-9)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

OPERATING EXPERIENCE WITH A NEAR-REAL-TIME INVENTORY BALANCE IN A NUCLEAR-FUEL-CYCLE PLANT. (CONF ; CONF-811097-2)

OPERATING EXPERIENCE WITH A NEAR-REAL-TIME INVENTORY BALANCE IN A NUCLEAR-FUEL-CYCLE PLANT. (CONF ; CONF-811097-2)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

REAL TIME MATERIAL ACCOUNTABILITY IN A CHEMICAL REPROCESSING UNIT. (CONF ; CONF-790707-17)

REAL TIME MATERIAL ACCOUNTABILITY IN A CHEMICAL REPROCESSING UNIT. (CONF ; CONF-790707-17)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

LINEAR FILTERING APPLIED TO MONTE CARLO CRITICALITY CALCULATIONS. (CONF ; CONF-751101-30)

LINEAR FILTERING APPLIED TO MONTE CARLO CRITICALITY CALCULATIONS. (CONF ; CONF-751101-30)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

DECAY HEAT ANALYSIS FOR AN LMFBR FUEL ASSEMBLY USING ENDF/IV DATA. (CONF ; CONF-750303-29)

DECAY HEAT ANALYSIS FOR AN LMFBR FUEL ASSEMBLY USING ENDF/IV DATA. (CONF ; CONF-750303-29)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

ENHANCEMENT OF KALMAN FILTER SINGLE LOSS DETECTION CAPABILITY. (CONF ; CONF-800655-15)

ENHANCEMENT OF KALMAN FILTER SINGLE LOSS DETECTION CAPABILITY. (CONF ; CONF-800655-15)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

COUPLED NEUTRON AND GAMMA RAY MULTIGROUP CROSS SECTION LIBRARY FOR USE N SHIELDING CALCULATIONS. (CONF ; CONF-720607-8)

COUPLED NEUTRON AND GAMMA RAY MULTIGROUP CROSS SECTION LIBRARY FOR USE N SHIELDING CALCULATIONS. (CONF ; CONF-720607-8)
Paper図書
MORRISON, G.W.
Other Libraries in Japan
  • Author HeadingMORRISON, G.W.

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