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INFLUENCE OF MAINTENANCE SYSTEM RELIABILITY AND MAINTAINABILITY CHARACTERISTICS ON OVERALL PLANT AVAILABILITY (CONF ; CONF-910102-3)

INFLUENCE OF MAINTENANCE SYSTEM RELIABILITY AND MAINTAINABILITY CHARACTERISTICS ON OVERALL PLANT AVAILABILITY (CONF ; CONF-910102-3)
紙図書
PRINCE, B.E.// HAIRE, M.J. (OAK RIDGE NATIONAL LAB., TN (USA))1991.
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  • 著者標目PRINCE, B.E. HAIRE, M.J.

Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle (ORNL ; ORNL/TM-11466)

Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle (ORNL ; ORNL/TM-11466)
紙図書
J.T. Bell [et al.]1990
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  • 著者標目...Forsberg, C.W. Prince, B.E. Bond, W.D. Campbell, D.O. Del...

EVALUATION OF NUCLEAR FUEL REPROCESSING STRATEGIES. 2. (K ; K-OP-299-PT.2)

EVALUATION OF NUCLEAR FUEL REPROCESSING STRATEGIES. 2. (K ; K-OP-299-PT.2)
紙図書
PRINCE, B.E.(et al.)1983.
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  • 著者標目PRINCE, B.E.

EVALUATION OF NUCLEAR FUEL REPROCESSING STRATEGIES. 1. (K ; K-OP-299-PT.1)

EVALUATION OF NUCLEAR FUEL REPROCESSING STRATEGIES. 1. (K ; K-OP-299-PT.1)
紙図書
PRINCE, B.E.(et al.)1982.
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  • 著者標目PRINCE, B.E.

ANALYSIS OF CHANGES IN NATIONAL ENERGY FORECASTS DURING THE 1970S. (K ; K-OP-276)

ANALYSIS OF CHANGES IN NATIONAL ENERGY FORECASTS DURING THE 1970S. (K ; K-OP-276)
紙図書
PRINCE, B.E.1980.
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  • 著者標目PRINCE, B.E.

SURVEY OF NUCLEAR FUEL CYCLE ECONOMICS: 1970-1985. (ORNL ; ORNL-TM-5703)

SURVEY OF NUCLEAR FUEL CYCLE ECONOMICS: 1970-1985. (ORNL ; ORNL-TM-5703)
紙図書
PRINCE, B.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1977.
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  • 著者標目PRINCE, B.E.

USE OF INCREMENTAL ENERGY COSTS AND LOADING ORDER RULES IN THE ORSIM PROCEDURE FOR MIDRANGE OPTIMIZATION OF ELECTRIC UTILITY OPERATIONS. (ORNL ; ORNL-TM-4507)

USE OF INCREMENTAL ENERGY COSTS AND LOADING ORDER RULES IN THE ORSIM PROCEDURE FOR MIDRANGE OPTIMIZATION OF ELECTRIC UTILITY OPERATIONS. (ORNL ; ORNL-TM-4507)
紙図書
PRINCE, B.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1975.
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  • 著者標目PRINCE, B.E.

IMPROVED REPRESENTATION OF SOME ASPECTS OF CIRCULATING-FUEL REACTOR KINETICS. (ORNL ; ORNL-TM-4179)

IMPROVED REPRESENTATION OF SOME ASPECTS OF CIRCULATING-FUEL REACTOR KINETICS. (ORNL ; ORNL-TM-4179)
紙図書
PRINCE, B.E.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1973.
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  • 著者標目PRINCE, B.E.

REACTIVITY BALANCE CALCULATIONS AND LONG-TERM REACTIVITY BEHAVIOR WITH U-235 THE MSRE. (ORNL ; ORNL-4674)

REACTIVITY BALANCE CALCULATIONS AND LONG-TERM REACTIVITY BEHAVIOR WITH U-235 THE MSRE. (ORNL ; ORNL-4674)
紙図書
PRINCE, B.E.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1972.
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  • 著者標目PRINCE, B.E.

PERIOD MEASUREMENTS ON THE MOLTEN SALT REACTOR EXPERIMENT DURING FUEL CIRCULATION: THEORY AND EXPERIMENT. (ORNL ; ORNL-TM-1626)

PERIOD MEASUREMENTS ON THE MOLTEN SALT REACTOR EXPERIMENT DURING FUEL CIRCULATION: THEORY AND EXPERIMENT. (ORNL ; ORNL-TM-1626)
紙図書
PRINCE, B.E.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
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  • 著者標目PRINCE, B.E.

Zero-power physics experiments on the molten-salt reactor experiment (ORNL ; ORNL-4233)

Zero-power physics experiments on the molten-salt reactor experiment (ORNL ; ORNL-4233)
紙図書
B.E. Prince [et al.]Oak Ridge National Lab.1968.
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  • 著者標目Prince, B.E. Ball, S.J. Engel, J.R. Hauben...

TEMPERATURE AND REACTIVITY COEFFICIENT AVERAGING IN THE MSRE (ORNL-TM ; ORNL-TM-379)

TEMPERATURE AND REACTIVITY COEFFICIENT AVERAGING IN THE MSRE (ORNL-TM ; ORNL-TM-379)
紙図書
1962.
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A REVIEW OF REACTIVITY LIFETIME ANALYSIS FOR CONTINUOUSLY FUELED, SOLID FUEL REACTORS (CF ; CF-61-4-100)

A REVIEW OF REACTIVITY LIFETIME ANALYSIS FOR CONTINUOUSLY FUELED, SOLID FUEL REACTORS (CF ; CF-61-4-100)
紙図書
Oak Ridge National Lab.1961.
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Temperature and reactivity coefficient averaging in the MSRE (ORNL-TM ; ORNL-TM-379)

Temperature and reactivity coefficient averaging in the MSRE (ORNL-TM ; ORNL-TM-379)
紙図書
B.E. Prince, J.R. EngelOak Ridge National Lab.1962.10.15.
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  • 著者標目Prince, B.E. Engel, J.R.

POISON ROD REQUIREMENTS FOR A SOLID-FUEL LEACHER TANK (CF ; CF-59-3-7)

POISON ROD REQUIREMENTS FOR A SOLID-FUEL LEACHER TANK (CF ; CF-59-3-7)
紙図書
Oak Ridge National Lab.1959.
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DUMP TANK CRITICALITY AND POISONS FOR SLURRY REACTORS. (ORNL ; ORNL-2708)

DUMP TANK CRITICALITY AND POISONS FOR SLURRY REACTORS. (ORNL ; ORNL-2708)
紙図書
PRINCE, B.E.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1959.
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  • 著者標目PRINCE, B.E.

SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL ONE-REGION SLURRY REACTORS: PART II (CF ; CF-58-11-98)

SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL ONE-REGION SLURRY REACTORS: PART II (CF ; CF-58-11-98)
紙図書
Oak Ridge National Lab.1958.
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CRITICALITY IN DUMP TANKS FOR HRE-3 BLANKET (CF ; CF-58-1-124)

CRITICALITY IN DUMP TANKS FOR HRE-3 BLANKET (CF ; CF-58-1-124)
紙図書
Oak Ridge National Lab.1958.
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SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL ONE-REGION SLURRY REACTORS. PART III (CF ; CF-58-12-15)

SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL ONE-REGION SLURRY REACTORS. PART III (CF ; CF-58-12-15)
紙図書
Oak Ridge National Lab.1958.
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SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL, ONE-REGION SLURRY REACTORS (CF ; CF-58-7-76)

SURVEY OF THE STATIC NUCLEAR CHARACTERISTICS OF SMALL, ONE-REGION SLURRY REACTORS (CF ; CF-58-7-76)
紙図書
Oak Ridge National Lab.1958.
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