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

Han et al., 2003 - Google Patents

Extraction of HNO3 and some ions with tributyl phosphate (TBP)-mixed trialkyl phosphine oxides (TRPO)/kerosene

Han et al., 2003

Document ID
20399190907162287
Author
Han B
Wu Q
Zhu Y
Wickramasinghe S
Publication year
Publication venue
Chemical Engineering Communications

External Links

Snippet

Tributyl phosphate (TBP) and trialkyl phosphine oxides (TRPO) are important extractants. They are widely used in industrial extraction processes, especially in the nuclear power industry. However, both TBP and TRPO suffer from several disadvantages. TBP has a low …
Continue reading at www.tandfonline.com (other versions)

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/16Processing by fixation in stable solid media
    • G21F9/162Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/16Processing by fixation in stable solid media
    • G21F9/167Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • G21F9/002Decontamination of the surface of objects with chemical or electrochemical processes
    • G21F9/004Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfaces

Similar Documents

Publication Publication Date Title
Manchanda et al. Amides and diamides as promising extractants in the back end of the nuclear fuel cycle: an overview
Horwitz et al. SREX: a newprocess for the extraction and recovery of strontium from acidic nuclear waste streams
Mathur et al. Extraction of actinides and fission products by octyl (phenyl)-N, N-diisobutylcarbamoylmethyl-phosphine oxide from nitric acid media
Pathak N, N-Dialkyl amides as extractants for spent fuel reprocessing: an overview
Madic et al. Actinide partitioning from high level liquid waste using the DIAMEX process
Pai et al. Extraction of plutonium (IV), uranium (VI) and some fission products by di-n-hexyl sulphoxide
Hasan et al. Tri-iso-amyl phosphate (TAP): an alternative extractant to tri-butyl phosphate (TBP) for reactor fuel reprocessing
Jose et al. Studies on the separation of Am (III) from trivalent lanthanides in high-level waste solution using modifier-free solvents and aqueous soluble bis-1, 2, 4-triazines
Veselsky Problems in the determination of plutonium in bioassay and environmental analysis
McCown et al. Radiochemical determination of cerium by liquid-liquid extraction
JPH10115695A (en) Method for selective separation of actinoids (iii) and lanthanoids (iii)
Kumari et al. Development of solvent extraction scheme for reprocessing of advanced heavy water reactor spent fuel using N, N-Dihexyl octanamide as extractant
Pathak et al. Distribution studies on Th (IV), U (VI) and Pu (IV) using tri-n-butylphosphate and N, N-dialkyl amides
Mathur et al. Recovery of neptunium from highly radioactive waste solutions of purex origin using tributyl phosphate
Tachimori et al. Extraction of some elements by mixture of DIDPA-TBP and its application to actinoid partitioning process
Kumari et al. Solvent extraction studies of protactinium for its recovery from short-cooled spent fuel and high-level waste solutions in thorium fuel cycle using diisobutyl carbinol (DIBC) as extractant
Han et al. Extraction of HNO3 and some ions with tributyl phosphate (TBP)-mixed trialkyl phosphine oxides (TRPO)/kerosene
Chao et al. Sequential extraction separation for determination of technetium-99 in radwastes by ICP-MS
Jianchen et al. Hot test of partitioning strontium from high-level liquid waste (HLLW) by dicyclohexano-18crown-6 (DCH18C6)
Metwally et al. Extraction of europium (III) and cobalt (II) by N, N, N’, N’-tetraoctyldiglycolamide and N, N, N’, N’-tetrahexyldiglycolamide from aqueous acid solutions
Boyarintsev et al. Liquid–liquid extraction of trivalent americium from carbonate and carbonate–peroxide aqueous solutions by methyltrioctylammonium carbonate in toluene
Ravi et al. Co-extraction and stripping behavior of trivalent actinides and fission products in N, N-di-2-ethylhexyl-N, N-dioctyl-diglycolamide
Shukla et al. Extraction of uranium (VI), plutonium (IV) and some fission products by tri-iso-amyl phosphate
Myasoedov et al. Recovery of U and Pu from simulated spent nuclear fuel by adducts of organic reagents with HNO3 followed by their separation from fission products by countercurrent chromatography
Sengupta et al. Separation and purification of americium from analytical waste solutions