Author: Donald Lee MarshPublisher:
ISBN:
Category :
Languages : en
Pages : 374
Book Description
Design of a Solvent Extraction Process to Separate Plutonium and Neptunium
Author: Donald Lee MarshNeptunium-237; Production and Recovery
Author: Wallace W. SchulzPublisher:
ISBN:
Category : Science
Languages : en
Pages : 100
Book Description
Tracer experiments on the solvent extraction of neptunium and plutonium
Author: Jacob KooiChemical Methods for the Purification and Isolation of Neptunium
Author: L. B. MagnussonPublisher:
ISBN:
Category : Chemicals
Languages : en
Pages : 0
Book Description
The best methods at the present time for separating neptunium from various types of source material are outlined. For the purpose of analytical classification neptunium may be grouped with uranium and plutonium since all three elements, mixed in an aqueous solution, can be oxidized to a characteristic +6 state. An excellent separation from other metal ions is obtained by extraction of the +6 states into diethyl either. Methyl isobutyl ketone is also an effective extracting solvent although it is not as specific. All three elements in the +6 state will precipitate with sodium as double acetates of the formul NaXO2 (OOCCH3)3. Neptunium may be separated from uranium and plutonium by solvent extraction and precipitation. Np(IV) forms a benzene soluble, chelate complex with thenoyl trifluoroacetone. Under suitable reducing conditions Np(IV) can be extracted away from Pu(III) and U(VI). A separation method involving the precipitation of fluorides is essentially dependent on the relative rates of oxidation and reduction of uranium, neptunium, and plutonium.
Liquid-Liquid Extraction Equipment
Author: J. C. GodfreyPublisher: Wiley
ISBN: 9780471941569
Category : Science
Languages : en
Pages : 788
Book Description
In recent years the use of liquid—liquid extraction equipment has attracted widespread interest from all major chemical engineering, petroleum and pharmaceutical companies as well as university-based scientists and engineers. Liquid—Liquid Extraction Equipment presents : a critical analysis of all available information, including practical recommendations new ideas on performance enhancement and equipment selection an up-to-date review of research results on equipment performance illustrations of present understanding using well-known equipment a concise survey of past, present and forthcoming procedures The combination of the historical aspects of the subject, with extensive references and illustrations, make this a unique information source. All researchers, in industry and academia, using this type of equipment will find Liquid—Liquid Extraction Equipment an authoritative reference work and a solid basis for future research projects.
DBBP Solvent Extraction Recovery of Neptunium and Plutonium from Purex 1WW Solution
Author: PLUTONIUM-238 RECOVERY FROM IRRADIATED NEPTUNIUM TARGETS USING SOLVENT EXTRACTION.
Author: Bruce MincherPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The United States Department of Energy proposes to re-establish a domestic capability for producing plutonium-238 (238Pu) to fuel radioisotope power systems primarily in support of future space missions. A conceptual design report is currently being prepared for a new 238Pu, and neptunium-237 (237Np) target fabrication and processing facility tentatively to be built at the Idaho National Laboratory (INL) in the USA. The facility would be capable of producing at least 5 kg of 238Pu-oxide powder per year. Production of 238Pu requires fabrication of 237Np targets with subsequent irradiation in the existing Advanced Test Reactor (ATR) located at the INL. The targets are 237Np oxide dispersed in a compact of powdered aluminum and clad with aluminum metal. The 238Pu product is separated and purified from the residual 237Np, aluminum matrix, and fission products. The unconverted 237Np is also a valuable starting material and is separated, purified and recycled to the target fabrication process. The proposed baseline method for separating and purifying 238Pu and unconverted 237Np post irradiation is by anion exchange (IX). Separation of Pu from Np by IX was chosen as the baseline method because of the method's proven ability to produce a quality Pu product and because it is amenable to the relatively small scale, batch type production methods used (small batches of ~200g 238Pu are processed at a time). Multiple IX cycles are required involving substantial volumes of nitric acid and other process solutions which must be cleaned and recycled or disposed of as waste. Acid recycle requires rather large evaporator systems, including one contained in a hot cell for remote operation. Finally, the organic based anion exchange resins are rapidly degraded due to the high a-dose and associated heat production from 238Pu decay, and must be regularly replaced (and disposed of as waste). In summary, IX is time consuming, cumbersome, and requires substantial tankage to accommodate the process. The primary purpose of the preliminary study discussed here is to develop an alternative process flowsheet using well-known solvent extraction (SX) techniques based on decades of experience with PUREX processing of nuclear materials. Ultimately, this initial study will be used to determine if an SX approach would offer any significant processing advantages relative to the currently proposed anion exchange process.
Developments in Solvent Extraction
Author: S. AlegretPublisher: Ellis Horwood
ISBN:
Category : Science
Languages : en
Pages : 232
Book Description
Extraction of Uranium, Neptunium and Plutonium from Caustic Media
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 5
Book Description
5 Fundamental research on uranium, neptunium and plutonium separation from alkaline media using solvent extraction is being conducted. Specific extractants for these actinides from alkaline media have been synthesized to investigate the feasibility of selective removal of these elements. Two families of extractants have been studied: terephthalamide and tetra(hydroxybenzyl)ethylene diamine derivatives. Fundamental studies were conducted to characterize their extraction behavior from a wide variety of aqueous conditions. The terephthalamide derivatives exhibit a significant extraction strength along with a discriminatory behavior among the actinides, plutonium being extracted the most strongly. Quantitative extraction of plutonium and moderate extraction of neptunium and uranium was achieved from a simple caustic solution. Interestingly, strontium is also quantitatively extracted by these derivatives. However, their stability to highly caustic solutions still needs to be imp roved. Tetra(hydroxybenzyl)ethylene diamine derivatives exhibit a very good stability to caustic conditions and are currently being studied.
Performance of a Plutonium Reflux Solvent Extraction System
Author: B. F. JudsonPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 30
Book Description