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BALL-MILLING OF GRAPHITE-BASE REACTOR FUEL. (ORNL ; ORNL-TM-1412)

BALL-MILLING OF GRAPHITE-BASE REACTOR FUEL. (ORNL ; ORNL-TM-1412)
Paper図書
WITTE, H.O.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan
  • Author HeadingWITTE, H.O.

SURVEY OF HEAD-END PROCESSES FOR THE RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE REACTOR FUELS. (ORNL ; ORNL-TM-1411)

SURVEY OF HEAD-END PROCESSES FOR THE RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE REACTOR FUELS. (ORNL ; ORNL-TM-1411)
Paper図書
WITTE, H.O.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan
  • Author HeadingWITTE, H.O.

CALCULATION OF FISSON PRODUCT RADIOACTIVITY IN OFF-GASES FROM A BURN-LEACH PROCESS FOR GRAPHITE-BASE FUELS. (ORNL ; ORNL-TM-1506)

CALCULATION OF FISSON PRODUCT RADIOACTIVITY IN OFF-GASES FROM A BURN-LEACH PROCESS FOR GRAPHITE-BASE FUELS. (ORNL ; ORNL-TM-1506)
Paper図書
WITTE, H.O.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1966.
Other Libraries in Japan
  • Author HeadingWITTE, H.O.

WASTE MANAGEMENT AND DISPOSAL I. (AED ; AED-CONF-75-769-136)

WASTE MANAGEMENT AND DISPOSAL I. (AED ; AED-CONF-75-769-136)
Paper図書
WITTE, H.O.
Other Libraries in Japan
  • Author HeadingWITTE, H.O.

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