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STATE-OF-THE ART SURVEY OF JOINABILITY OF MATERIALS FOR OTEC HEAT EXCHANGERS. (ORNL ; ORNL-TM-6284)

STATE-OF-THE ART SURVEY OF JOINABILITY OF MATERIALS FOR OTEC HEAT EXCHANGERS. (ORNL ; ORNL-TM-6284)
Paper図書
BEAVER, R.J.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1978.
Other Libraries in Japan

BORON CONCENTRATION GRADIENT FOR IMPROVED THERMAL REACTOR PERFORMANCE OF BORON STAINLESS STEEL CONTROL RODS. (ORNL ; ORNL-4877)

BORON CONCENTRATION GRADIENT FOR IMPROVED THERMAL REACTOR PERFORMANCE OF BORON STAINLESS STEEL CONTROL RODS. (ORNL ; ORNL-4877)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1973.
Other Libraries in Japan

STATUS OF EUROPIUM COMPOUNDS FOR REACTIVITY CONTROL IN NUCLEAR REACTORS. (ORNL ; ORNL-4368)

STATUS OF EUROPIUM COMPOUNDS FOR REACTIVITY CONTROL IN NUCLEAR REACTORS. (ORNL ; ORNL-4368)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1969.
Other Libraries in Japan

IRRADIATION BEHAVIOR OF ALUMINUM-BASE DISPERSIONS CONTAINING EUROPIUM OXIDES. (ORNL ; ORNL-4199)

IRRADIATION BEHAVIOR OF ALUMINUM-BASE DISPERSIONS CONTAINING EUROPIUM OXIDES. (ORNL ; ORNL-4199)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1968.
Other Libraries in Japan

INITIAL DEVELOPMENT OF HFIR FUEL ASSEMBLIES. (ORNL ; ORNL-4108)

INITIAL DEVELOPMENT OF HFIR FUEL ASSEMBLIES. (ORNL ; ORNL-4108)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1967.
Other Libraries in Japan

ESTIMATED LARGE-SCALE PRODUCTION COSTS FOR CLADDING URANIUM METAL FUEL TUBES. (ORNL ; ORNL-TM-596)

ESTIMATED LARGE-SCALE PRODUCTION COSTS FOR CLADDING URANIUM METAL FUEL TUBES. (ORNL ; ORNL-TM-596)
Paper図書
BEAVER, R.J.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan

SURVEY OF THE CORROSION OF MARTENSITIC AND FERRITIC STAINLESS STEELS IN PRESSURIZED WATER. (ORNL ; ORNL-TM-539)

SURVEY OF THE CORROSION OF MARTENSITIC AND FERRITIC STAINLESS STEELS IN PRESSURIZED WATER. (ORNL ; ORNL-TM-539)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1963.
Other Libraries in Japan

INVESTIGATION OF THE CORROSION RESISTANCE OF BRAZING ALLOYS FOR AUSTENITIC STAINLESS STEEL FUEL ELEMENTS FOR SERVICE IN 565 DEGREE F PRESSURIZED WATER. (ORNL ; ORNL-2834)

INVESTIGATION OF THE CORROSION RESISTANCE OF BRAZING ALLOYS FOR AUSTENITIC STAINLESS STEEL FUEL ELEMENTS FOR SERVICE IN 565 DEGREE F PRESSURIZED WATER. (ORNL ; ORNL-2834)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1962.
Other Libraries in Japan

CLADDING SURVEY FOR THE ENRICO FERMI REACTOR U-15 WT.% MO BASE DISPERSION- TYPE FUEL ELEMENT (CF ; CF-60-4-118)

CLADDING SURVEY FOR THE ENRICO FERMI REACTOR U-15 WT.% MO BASE DISPERSION- TYPE FUEL ELEMENT (CF ; CF-60-4-118)
Paper図書
Oak Ridge National Lab.1960.
Other Libraries in Japan
  • Author HeadingMartin, M M Beaver, R J

INVESTIGATION OF THE FACTORS AFFECTING SENSITIZATION OF ARMY PACKAGE POWER REACTOR (APPR-1) FUEL ELEMENTS. (ORNL ; ORNL-2312)

INVESTIGATION OF THE FACTORS AFFECTING SENSITIZATION OF ARMY PACKAGE POWER REACTOR (APPR-1) FUEL ELEMENTS. (ORNL ; ORNL-2312)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1957.
Other Libraries in Japan

SPECIFICATIONS FOR ARMY PACKAGE POWER REACTOR (APPR-1) FUEL AND CONTROL ROD COMPONENTS. (ORNL ; ORNL-2225)

SPECIFICATIONS FOR ARMY PACKAGE POWER REACTOR (APPR-1) FUEL AND CONTROL ROD COMPONENTS. (ORNL ; ORNL-2225)
Paper図書
BEAVER, R.J.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1957.
Other Libraries in Japan

SPECIFICATIONS AND FABRICATION PROCEDURES FOR APPR-1 CORE II STATIONARY FUEL ELEMENTS (CF ; CF-58-7-72)

SPECIFICATIONS AND FABRICATION PROCEDURES FOR APPR-1 CORE II STATIONARY FUEL ELEMENTS (CF ; CF-58-7-72)
Paper図書
Oak Ridge National Lab.1958.
Other Libraries in Japan
  • Author HeadingCunningham, J E Beaver, R J

IRRADIATION EXPERIMENT ON ALUMINUM FUEL ELEMENT CONTAINING U$SUB 3$O$SUB 8$ DISPERSION (CF ; CF-56-12-116(REV.))

IRRADIATION EXPERIMENT ON ALUMINUM FUEL ELEMENT CONTAINING U$SUB 3$O$SUB 8$ DISPERSION (CF ; CF-56-12-116(REV.))
Paper図書
Oak Ridge National Lab.1957.
Other Libraries in Japan
  • Author HeadingBeaver, R J

IRRADIATION EXPERIMENT ON ALUMINUM FUEL PLATES CONTAINING A 48 WT. % URANIUM-3 WT. % SILICON-49 WT. % ALUMINUM ALLOY WITH 20% ENRICHMENT IN THE U-235 ISOTOPE (CF ; CF-57-7-100)

IRRADIATION EXPERIMENT ON ALUMINUM FUEL PLATES CONTAINING A 48 WT. % URANIUM-3 WT. % SILICON-49 WT. % ALUMINUM ALLOY WITH 20% ENRICHMENT IN THE U-235 ISOTOPE (CF ; CF-57-7-100)
Paper図書
Oak Ridge National Lab.1957.
Other Libraries in Japan
  • Author HeadingBeaver, R J

EFFECT OF PRESSURE DIFFERENTIALS ON DEFLECTION OF THE OUTER FUEL PLATES OF BRAZED APPR FUEL ELEMENTS (CF ; CF-57-2-34)

EFFECT OF PRESSURE DIFFERENTIALS ON DEFLECTION OF THE OUTER FUEL PLATES OF BRAZED APPR FUEL ELEMENTS (CF ; CF-57-2-34)
Paper図書
Oak Ridge National Lab.1957.
Other Libraries in Japan
  • Author HeadingErwin, J H Beaver, R J

RECENT DEVELOPMENTS IN THE POWDER METALLURGY APPLICATION OF URANIUM OXIDES TO ALUMINUM RESEARCH REACTOR FUEL ELEMENTS (CF ; CF-57-9-60)

RECENT DEVELOPMENTS IN THE POWDER METALLURGY APPLICATION OF URANIUM OXIDES TO ALUMINUM RESEARCH REACTOR FUEL ELEMENTS (CF ; CF-57-9-60)
Paper図書
Oak Ridge National Lab.1957.
Other Libraries in Japan

MANUFACTURING U-AL FUEL PLATES CLAD WITH AN INTENDED 99.90 W/O AL-0.10 W/O B ALLOY (CF ; CF-56-4-64)

MANUFACTURING U-AL FUEL PLATES CLAD WITH AN INTENDED 99.90 W/O AL-0.10 W/O B ALLOY (CF ; CF-56-4-64)
Paper図書
Oak Ridge National Lab.1956.
Other Libraries in Japan

MINUTES OF MEETING TO CLARIFY STATUS OF APPR-1 FUEL ELEMENTS (CF ; CF-56-7-149)

MINUTES OF MEETING TO CLARIFY STATUS OF APPR-1 FUEL ELEMENTS (CF ; CF-56-7-149)
Paper図書
Oak Ridge National Lab.1956.
Other Libraries in Japan
  • Author HeadingBeaver, R J

IRRADIATION EXPERIMENT ON ALUMINUM FUEL ELEMENT CONTAINING U$SUB 3$O$SUB 8$ DISPERSION (CF ; CF-56-12-116)

IRRADIATION EXPERIMENT ON ALUMINUM FUEL ELEMENT CONTAINING U$SUB 3$O$SUB 8$ DISPERSION (CF ; CF-56-12-116)
Paper図書
Oak Ridge National Lab.1956.
Other Libraries in Japan
  • Author HeadingBeaver, R J

IRRADIATION EXPERIMENT ON ALUMINUM FUEL PLATES CONTAINING A 48 W/O URANIUM - 52 W/O ALUMINUM ALLOY, WITH A 20% ENRICHMENT IN THE U-235 ISOTOPE (CF ; CF-56-6-148)

IRRADIATION EXPERIMENT ON ALUMINUM FUEL PLATES CONTAINING A 48 W/O URANIUM - 52 W/O ALUMINUM ALLOY, WITH A 20% ENRICHMENT IN THE U-235 ISOTOPE (CF ; CF-56-6-148)
Paper図書
Oak Ridge National Lab.1956.
Other Libraries in Japan
  • Author HeadingBeaver, R J
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