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AMERICIUM PRODUCT SOLIDIFICATION AND DISPOSAL. (ORNL ; ORNL-TM-10226)

AMERICIUM PRODUCT SOLIDIFICATION AND DISPOSAL. (ORNL ; ORNL-TM-10226)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1987.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

HOW WELL DOES ORIGEN PREDICT SPENT LWR (LIGHT WATER REACTOR) FUEL CHARACTERISTICS. (CONF ; CONF-870306-7)

HOW WELL DOES ORIGEN PREDICT SPENT LWR (LIGHT WATER REACTOR) FUEL CHARACTERISTICS. (CONF ; CONF-870306-7)
Paper図書
MAILEN, J.C.(et al.)1987.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

SECONDARY SOLVENT CLEANUP USING ACTIVATED ALUMINA: LABORATORY DEVELOPMENT. (CONF ; CONF-871101-2)

SECONDARY SOLVENT CLEANUP USING ACTIVATED ALUMINA: LABORATORY DEVELOPMENT. (CONF ; CONF-871101-2)
Paper図書
MAILEN, J.C.1987.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

RECOVERY OF URANIUM FROM 30 VOL % TRIBUTYL PHOSPHATE SOLVENTS CONTAINING DIBUTYL PHOSPHATE. (CONF ; CONF-860411-3)

RECOVERY OF URANIUM FROM 30 VOL % TRIBUTYL PHOSPHATE SOLVENTS CONTAINING DIBUTYL PHOSPHATE. (CONF ; CONF-860411-3)
Paper図書
MAILEN, J.C.(et al.)1986.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

SEPARATION OF URANIUM AND DIBUTYL PHOSPHATE CONTAINED IN 30 VOL % TRIBUTYL PHOSPHATE SOLVENTS. (ORNL ; ORNL-TM-9837)

SEPARATION OF URANIUM AND DIBUTYL PHOSPHATE CONTAINED IN 30 VOL % TRIBUTYL PHOSPHATE SOLVENTS. (ORNL ; ORNL-TM-9837)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1986.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

POTENTIAL FOR THE USE OF HYDROCHLORIC ACID IN FISSION REACTOR FUEL RECYCLE. (CONF ; CONF-851011-8)

POTENTIAL FOR THE USE OF HYDROCHLORIC ACID IN FISSION REACTOR FUEL RECYCLE. (CONF ; CONF-851011-8)
Paper図書
MAILEN, J.C.(et al.)1985.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

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)
Paper図書
J.T. Bell [et al.]1990
Other Libraries in Japan
  • Author Heading.... Delene, J.G. Mailen, J.C.

CLEANUP OF SAVANNAH RIVER PLANT SOLVENT USING SOLID SORBENTS. (ORNL ; ORNL-TM-9256)

CLEANUP OF SAVANNAH RIVER PLANT SOLVENT USING SOLID SORBENTS. (ORNL ; ORNL-TM-9256)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1985.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

SECONDARY CLEANUP OF IDAHO CHEMICAL PROCESSING PLANT SOLVENT. (CONF ; CONF-851011-9)

SECONDARY CLEANUP OF IDAHO CHEMICAL PROCESSING PLANT SOLVENT. (CONF ; CONF-851011-9)
Paper図書
MAILEN, J.C.1985.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

SOLVENT DEGRADATION AND CLEANUP: A SURVEY AND RECENT ORNL STUDIES. (CONF ; CONF-840802-15)

SOLVENT DEGRADATION AND CLEANUP: A SURVEY AND RECENT ORNL STUDIES. (CONF ; CONF-840802-15)
Paper図書
MAILEN, J.C.(et al.)1984.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

IMPROVED PUREX SOLVENT SCRUBBING METHODS. (CONF ; CONF-840802-10)

IMPROVED PUREX SOLVENT SCRUBBING METHODS. (CONF ; CONF-840802-10)
Paper図書
MAILEN, J.C.(et al.)1984.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

ASSESSMENT OF PUREX SOLVENT CLEANUP METHODS USING A MIXER-SETTLER SYSTEM. (ORNL ; ORNL-TM-9118)

ASSESSMENT OF PUREX SOLVENT CLEANUP METHODS USING A MIXER-SETTLER SYSTEM. (ORNL ; ORNL-TM-9118)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1984.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

DESTRUCTION OF OXALATE BY REACTION WITH HYDROGEN PEROXIDE. (ORNL ; ORNL-TM-7474)

DESTRUCTION OF OXALATE BY REACTION WITH HYDROGEN PEROXIDE. (ORNL ; ORNL-TM-7474)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1981.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

USE OF CHEMICAL EQUILIBRIUM DATA TO CALCULATE IODOX COLUMN OPERATIONS. (ORNL ; ORNL-TM-5077)

USE OF CHEMICAL EQUILIBRIUM DATA TO CALCULATE IODOX COLUMN OPERATIONS. (ORNL ; ORNL-TM-5077)
Paper図書
MAILEN, J.C.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1975.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

HOT-CELL STUDIES OF THE FLUIDIZED-BED FLUORIDE VOLATILITY PROCESS FOR RECOVERING URANIUM AND PLUTONIUM FROM SPENT UO2 FUELS. (ORNL ; ORNL-TM-2170)

HOT-CELL STUDIES OF THE FLUIDIZED-BED FLUORIDE VOLATILITY PROCESS FOR RECOVERING URANIUM AND PLUTONIUM FROM SPENT UO2 FUELS. (ORNL ; ORNL-TM-2170)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1969.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

FLUORINATION OF FALLING DROPLETS OF MOLTEN FLUORIDE SALT AS A MEANS OF RECOVERING URANIUM AND PLUTONIUM. (ORNL ; ORNL-4224)

FLUORINATION OF FALLING DROPLETS OF MOLTEN FLUORIDE SALT AS A MEANS OF RECOVERING URANIUM AND PLUTONIUM. (ORNL ; ORNL-4224)
Paper図書
MAILEN, J.C.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1968.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

VOLATILIZATION OF URANIUM AS THE HEXAFLUORIDE FROM DROPS OF MOLTEN FLUORIDE SALT. NEARLY COMPLETE VOLATILIZATION OF URANIUM FROM MOLTEN FLUORIDE SALT DROPLETS 100 p IN DIAMETER IS POSSIBLE WITH A 3-SEC EXPOSURE TO FLUORINE AT 600 DEGREE. (ORNL ; ORNL-P-279)

VOLATILIZATION OF URANIUM AS THE HEXAFLUORIDE FROM DROPS OF MOLTEN FLUORIDE SALT. NEARLY COMPLETE VOLATILIZATION OF URANIUM FROM MOLTEN FLUORIDE SALT DROPLETS 100 p IN DIAMETER IS POSSIBLE WITH A 3-SEC EXPOSURE TO FLUORINE AT 600 DEGREE. (ORNL ; ORNL-P-279)
Paper図書
MAILEN, J.C.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1962.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

REACTOR COOLANT DECONTAMINATION: A LITERATURE SURVEY (CF ; CF-59-10-124)

REACTOR COOLANT DECONTAMINATION: A LITERATURE SURVEY (CF ; CF-59-10-124)
Paper図書
Oak Ridge National Lab.1959.
Other Libraries in Japan

SEPARATION OF CALIFORNIUM FROM OTHER ACTINIDES. (US-PATENT-DOCUMENT ; US-PAT-3761564)

SEPARATION OF CALIFORNIUM FROM OTHER ACTINIDES. (US-PATENT-DOCUMENT ; US-PAT-3761564)
Paper図書
MAILEN, J.C.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.

REVIEW OF RECENT ORNL STUDIES IN SOLVENT CLEANUP AND DILUENT DEGRADATION.:CONSOLIDATE FUEL-REPROCESSING PROGRAM. (CONF ; CONF-821056-8)

REVIEW OF RECENT ORNL STUDIES IN SOLVENT CLEANUP AND DILUENT DEGRADATION.:CONSOLIDATE FUEL-REPROCESSING PROGRAM. (CONF ; CONF-821056-8)
Paper図書
MAILEN, J.C.
Other Libraries in Japan
  • Author HeadingMAILEN, J.C.
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