Title:
【発明の名称】使用済核燃料の乾式再処理で発生する廃棄塩中のプルトニウムの回収方法
Document Type and Number:
Japanese Patent JP2941740
Kind Code:
B2
Abstract:
PROBLEM TO BE SOLVED: To improve the recovery efficiency of plutonium in dry reprocessing and improve the production efficiency of the plant. SOLUTION: Waste salt in a rotary cathode electrolysis tank 30 is sucked by a pump 48 and transported through a pipe 46 to a waste salt oxidizing tank 100. In this salt phase, lanthanoide and actinoid remain in the form of chloride. Thus, oxygen is introduced in the waste salt oxidizing tank 100 through a pipe 112 to oxidize plutonium existing in the waste salt. Then, with a pump 108, the oxide is sucked together with the waste salt and transported to a solid/ liquid separator 104 of centrifugal separation type. The oxide is separated by the centrifugal separator and only waste salt is returned to the waste salt oxidizing tank 100.
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Inventors:
AMAMOTO ITSUPEI
IGARASHI MYUKI
IGARASHI MYUKI
Application Number:
JP14481197A
Publication Date:
August 30, 1999
Filing Date:
June 03, 1997
Export Citation:
Assignee:
KAKUNENRYO SAIKURU KAIHATSU KIKO
International Classes:
G21C19/44; G21F9/06; (IPC1-7): G21C19/44; G21F9/06
Attorney, Agent or Firm:
Kenji Yoshida (2 outside)