Han et al., 2003 - Google Patents
Extraction of HNO3 and some ions with tributyl phosphate (TBP)-mixed trialkyl phosphine oxides (TRPO)/keroseneHan 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 …
- 239000003350 kerosene 0 title abstract description 72
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
- G21F9/16—Processing by fixation in stable solid media
- G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
-
- 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
- G21F9/16—Processing by fixation in stable solid media
- G21F9/167—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
-
- 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
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
- G21F9/002—Decontamination of the surface of objects with chemical or electrochemical processes
- G21F9/004—Decontamination 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 |