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- ARAI Kazuhiro
- Ishikawajima-Harima Heavy Industries Co., Ltd.
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- YAMASHITA Masatada
- Ishikawajima-Harima Heavy Industries Co., Ltd.
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- HATTA Masahisa
- Ishikawajima-Harima Heavy Industries Co., Ltd.
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- TOMIYASU Hiroshi
- Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
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- IKEDA Yasuhisa
- Nuclear Chemistry and Chemical Engineering Center, Institute of Research and Innovation
書誌事項
- タイトル別名
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- Modified TRUEX Process for the Treatmen
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The TRUEX process has been examined to recover Am and Cm from the high-level liquid waste of Purex reprocessing plant. Continuous counter current extraction and back-extraction experiments were carried out by a mixersettler using simulated waste solution for three process flowsheets, i.e. a process flowsheet developed by Argonne National Laboratory and other two process flowsheets which were modified in the scrub stage. The result indicates that the process flowsheet of Argonne National Laboratory cannot be applied for the high-level liquid waste containing high concentrations of lanthanide and actinide elements because of the formation of insoluble salts of these elements with oxalic acid, which is added to restrict the extraction of fission products such as Mo and Zr. A modified process flowsheet, which had only one scrub stage with high concentration of nitric acid, was found to be the best of three process flowsheets examined, where Nd as a simulated element of Am and Cm was sufficiently recovered and any precipitation of oxalate salt was not observed.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 34 (5), 521-526, 1997
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001204094462080
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- NII論文ID
- 10002077249
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- NII書誌ID
- AA00703720
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- COI
- 1:CAS:528:DyaK2sXktFWrsrc%3D
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- ISSN
- 18811248
- 00223131
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- NDL書誌ID
- 4219701
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可