[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

Ansari et al., 2022 - Google Patents

Comparison of DHOA and TBP for uranium separation from acidic feeds using mixer-settlers

Ansari et al., 2022

Document ID
10975506098319505299
Author
Ansari S
Gujar R
Mohapatra P
Publication year
Publication venue
Proceedings of the tenth DAE-BRNS biennial symposium on emerging trends in separation science and technology: abstracts

External Links

Snippet

[en] Reprocessing of the spent fuel to recover U and Pu is an important part of the back-end of nuclear fuel cycle. Globally, 30% tributyl phosphate (TBP) in paraffinic solvent is employed for the extraction of U and Pu in the PUREX process. Though TBP is globally used …
Continue reading at inis.iaea.org (other versions)

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing

Similar Documents

Publication Publication Date Title
Ansari et al. Comparison of DHOA and TBP for uranium separation from acidic feeds using mixer-settlers
Velavendan et al. Studies on the behavior of zirconium on the removal of DBP from degraded solvent by sodium carbonate wash
Sreenivasulu et al. Recovery of Zr from raffinate solutions by cross-current mode extraction using trialkyl phosphate based solvents
Sinha et al. Studies on the extraction behaviour of Zr (IV) in HNO 3-TBP-HDBP/ndodecane system
Sinha et al. Studies on the role of dibutyl phosphoric acid on the retention of Zirconium (IV) in organic phase
Sreenivasulu et al. Studies related to the aqueous reprocessing of metallic alloy fuels using phosphonate based solvents
Subashree et al. U-Zr separation by cross-current mode using Tris (2-methylbutyl) Phosphate as the extractant
Sreenivasulu et al. Separation of U (VI) from Zr (IV) with tri-n-butyl phosphate (TBP) as the extractant by using an ejector mixer-settler
Rathore et al. Degradation studies of TBP in PUREX process streams
Dinkar et al. Separation of thorium from plutonium using organophosphorous extractant
Subashree et al. Separation of U (VI) from U-Th-Ce mixture using Tris (2-methylbutyl) phosphate as the extractant by cross current mode
Suba et al. Studies on third phase formation in U-Zr-HNO 3-TBP-NPH system
Sreenivasulu et al. Modeling and experimental study on mixer-settler runs for the extraction and stripping of uranium by TBP from U-Zr solutions
Thakur et al. Reactive stripping and precipitation of uranium in a microchannel
Takao Simple and versatile reprocessing method based on selective crystallization of nuclear fuel materials from HNO 3 (aq)
Velavendan et al. Studies on the removal of dissolved DBP in the aqueous streams of fuel reprocessing
Sreenivasulu et al. Studies related to processing of U–Zr Metallic Fuels using tri-iso-amyl; phosphate (TIAP) and tri-n-butyl phosphate (TBP) in n-dodecane
Ganesh et al. Comparative studies on the extraction of Th (IV) from nitric acid medium with 1.1 M TBP, TiAP-nDD mixture
Prathibha et al. Comparative evaluation of amides and TBP for removal of bulk uranium from dissolver solution of U-Zr slugs during impurity analysis
Sreenivasulu et al. Recovery of U (VI) and Th (IV) from rare earth elements using tri-iso-amyl phosphate by liquid-liquid extraction
Sivaramakrishna et al. Recovery of uranium by diamylamyl phosphonate from thiocyanate analytical waste
Rajani et al. Computational studies on complexation behaviour of methyl substituted phosphinic acids with U (VI)
Phadke et al. Distribution of thorium in PUREX process streams
Rao Comparative study on direct dissolution and uranium extraction using DHOA. HNO 3 adduct and room temperature ionic liquid/supercritical carbon dioxide
Mhatre et al. Preliminary studies on recovery of nitric acid from simulated raffinate of uranium extraction process using UV-grafted anion exchange membrane