Formation of precipitate in high-level liquid waste from nuclear fuel reprocessing.

• KUBOTA Masumitsu

  Japan Atomic Energy Research Institute

• FUKASE Tokunosuke

  Mitsubishi Chemical Industries Ltd.

抄録

Stability of high-level liquid waste (HLW) from nuclear fuel reprocessing was studied by using a simulated HLW. Fundamental works disclosed that precipitates formed during aging at ambient temperature or refiuxing the simulated HLW in 2 mol/l HNO₃ solution consist mainly of Mo, Zr and Te contributing significantly to the formation of precipitate. When the simulated HLW was denitrated with formic acid or deacidified with NaOH, fractions of precipitated Mo, Zr and Te increased with pH and amounted to over 85% at pH 0.5, where the fraction of precipitated La was below 0.1%. For further treatment of HLW such as partitioning, denitration of HLW to pH 0.5 might be useful for removing Mo, Zr and Te from the solution without significant contamination with rare earths, Am and Cm.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 17 (10), 783-790, 1980

  一般社団法人 日本原子力学会

キーワード

• high-level liquid waste
• nuclear fuel reprocessing
• fission products
• precipitation
• molybdenum
• zirconium
• tellurium
• zirconium molybdate
• denitralion
• formic acid
• pH value
• tranplutonium elements
• partitioning

詳細情報

• CRID: 1390001204094251776
• NII論文ID: 130000828637
• DOI: 10.3327/jnst.17.783
• COI: 1:CAS:528:DyaL3MXhvVSjt70%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可