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詳細

Significant amounts of uranium (U) and thorium (Th) exist in the earth ores and in the nuclear fuel reprocessing process, which needs separation and extraction. Reprocessing the spent fuel not only reduces the volume and radio toxicity of the high-level waste, but also can be used to produce new fuel.The separation techniques for reprocessing include precipitation, ion exchange, and solvent extraction. Solvent extraction has several advantages for use in the large scale reprocessing of spent nuclear fuel, including the ability for continuous operation, high throughput, and solvent recycling.

共演者・アシスタント

著者 Mazen Nazal

著者 Fawwaz Khalili

商品詳細

DUIN 1834G4642CV

GTIN 9783659193279

言語 英語

ページ数 92

Product type 文庫本

寸法 220 x 150  mm

Extraction of U(VI)From High Ionic Strength Solutions By (HDDPA)

Extraction of U(VI) From Perchlorate, Nitrate and Phosphate Solutions

Mazen Nazal

¥ 5,927

出品者 Dodax EU

配送日: 火曜日, 11月, 27 ~ 木曜日, 11月, 29 の間

コンディション: 新品

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