LABORATORY STUDIES ON THE USE OF URANIUM(IV) AS A PLUTONIUM REDUCTANT IN A PUREX PROCESS.

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Book Synopsis LABORATORY STUDIES ON THE USE OF URANIUM(IV) AS A PLUTONIUM REDUCTANT IN A PUREX PROCESS. by :

Download or read book LABORATORY STUDIES ON THE USE OF URANIUM(IV) AS A PLUTONIUM REDUCTANT IN A PUREX PROCESS. written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Laboratory Studies on the Use of Uranium(iv) as a Plutonium Reductant in a Purex Process

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ISBN 13 :
Total Pages : 22 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Laboratory Studies on the Use of Uranium(iv) as a Plutonium Reductant in a Purex Process by : J. E. Mendel

Download or read book Laboratory Studies on the Use of Uranium(iv) as a Plutonium Reductant in a Purex Process written by J. E. Mendel and published by . This book was released on 1965 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Studies on the Use of Uranium (iv) as a Reductant for Plutonium in Purex Process

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ISBN 13 :
Total Pages : 47 pages
Book Rating : 4.:/5 (13 download)

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Book Synopsis Studies on the Use of Uranium (iv) as a Reductant for Plutonium in Purex Process by : N. Srinivasan

Download or read book Studies on the Use of Uranium (iv) as a Reductant for Plutonium in Purex Process written by N. Srinivasan and published by . This book was released on 1968 with total page 47 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Use of Ferrous Nitrate as a Plutonium Reductant for Partitioning Plutonium and Uranium in Purex Processes

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ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (875 download)

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Book Synopsis The Use of Ferrous Nitrate as a Plutonium Reductant for Partitioning Plutonium and Uranium in Purex Processes by : D. E. Horner

Download or read book The Use of Ferrous Nitrate as a Plutonium Reductant for Partitioning Plutonium and Uranium in Purex Processes written by D. E. Horner and published by . This book was released on 1969 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate

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Book Synopsis Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate by :

Download or read book Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate (HAN) and ferrous sulfamate (FS) is superior to FS used alone as a reductant for plutonium in the Purex first cycle. FS usage has been reduced by about 70% (from 0.12 to 0.04M) compared to the pre-1978 period. This reduced the volume of neutralized waste due to FS by 194 liters/metric ton of uranium (MTU) processed. The new flowsheet also gives lower plutonium losses to waste and at least comparable fission product decontamination. To achieve satisfactory performance at this low concentration of FS, the acidity in the 1B mixer-settler was reduced by using a split-scrub - a low acid scrub in stage one and a higher acid scrub in stage three - to remove acid from the solvent exiting the 1A centrifugal contactor. 8 references, 14 figures, 1 table.

THE USE OF FERROUS NITRATE AS A PLUTONIUM REDUCTANT FOR PARTITIONING PLUTONIUM AND URANIUM IN PUREX PROCESSES.

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Book Rating : 4.:/5 (16 download)

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Book Synopsis THE USE OF FERROUS NITRATE AS A PLUTONIUM REDUCTANT FOR PARTITIONING PLUTONIUM AND URANIUM IN PUREX PROCESSES. by :

Download or read book THE USE OF FERROUS NITRATE AS A PLUTONIUM REDUCTANT FOR PARTITIONING PLUTONIUM AND URANIUM IN PUREX PROCESSES. written by and published by . This book was released on 1969 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Purex Process

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ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis The Purex Process by : E. R. Irish

Download or read book The Purex Process written by E. R. Irish and published by . This book was released on 1957 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Uranium(IV) Nitrate as a Reducing Agent for Plutonium(IV) in the Purex Process

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ISBN 13 :
Total Pages : 24 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Uranium(IV) Nitrate as a Reducing Agent for Plutonium(IV) in the Purex Process by :

Download or read book Uranium(IV) Nitrate as a Reducing Agent for Plutonium(IV) in the Purex Process written by and published by . This book was released on 1963 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Purex

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Purex by :

Download or read book Purex written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Purex process is the solvent extraction system that uses tributyl phosphate as the extractant for separating uranium and plutonium from irradiated reactor fuels. Since the first flowsheet was proposed at Oak Ridge National Laboratory in 1950, the process has endured for over 30 years with only minor modifications. The spread of the technology was rapid, and worldwide use or research on Purex-type processes was reported by the time of the 1955 Geneva Conference. The overall performance of the process has been so good that there are no serious contenders for replacing it soon. This paper presents: process description; equipment performance (mixer-settlers, pulse columns, rapid contactors); fission product decontamination; solvent effects (solvent degradation products); and partitioning of uranium and plutonium.

Reduction of Plutonium(IV) Using Photochemically Generated Uranium(IV).

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Book Synopsis Reduction of Plutonium(IV) Using Photochemically Generated Uranium(IV). by :

Download or read book Reduction of Plutonium(IV) Using Photochemically Generated Uranium(IV). written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The reduction of Pu(IV) using photochemically generated U(IV) has been evaluated as a procedure for possible inclusion in the Savannah River Plant's nuclear fuel reprocessing facility. The ''Purex 2nd Uranium Cycle'' with feed conditions of 400 g/L U, 1 M HNO3, and 10−8 to 10−6 M Pu was identified previously as the most promising stage for application of a photochemical method. Laboratory tests were conducted under similar conditions to determine if the plutonium could be successfully reduced and separated in a two-phase flowing system. The laboratory scale tests, which used primarily a 0.01 M butanol/0.01 M hydrazine reductant combination, demonstrated that reductive stripping of Pu(IV) using photochemically generated U(IV) is a practical method for removing plutonium from the organic phase. The kinetics of the reductive stripping procedure were found to be determined by the mixing rates of the organic and aqueous phases in this simple laboratory-scale system.

Use of Reductants in the Purification of Uranium by Purex Process

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ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (891 download)

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Book Synopsis Use of Reductants in the Purification of Uranium by Purex Process by : S.V. Kumar

Download or read book Use of Reductants in the Purification of Uranium by Purex Process written by S.V. Kumar and published by . This book was released on 1974 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Overview of Reductants Utilized in Nuclear Fuel Reprocessing/recycling

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (967 download)

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Book Synopsis Overview of Reductants Utilized in Nuclear Fuel Reprocessing/recycling by :

Download or read book Overview of Reductants Utilized in Nuclear Fuel Reprocessing/recycling written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Most of the aqueous processes developed, or under consideration worldwide for the recycling of used nuclear fuel (UNF) utilize the oxido-reduction properties of actinides to separate them from other radionuclides. Generally, after acid dissolution of the UNF, (essentially in nitric acid solution), actinides are separated from the raffinate by liquid-liquid extraction using specific solvents, associated along the process, with a particular reductant that will allow the separation to occur. For example, the industrial PUREX process utilizes hydroxylamine as a plutonium reductant. Hydroxylamine has numerous advantages: not only does it have the proper attributes to reduce Pu(IV) to Pu(III), but it is also a non-metallic chemical that is readily decomposed to innocuous products by heating. However, it has been observed that the presence of high nitric acid concentrations or impurities (such as metal ions) in hydroxylamine solutions increase the likelihood of the initiation of an autocatalytic reaction. Recently there has been some interest in the application of simple hydrophilic hydroxamic ligands such as acetohydroxamic acid (AHA) for the stripping of tetravalent actinides in the UREX process flowsheet. This approach is based on the high coordinating ability of hydroxamic acids with tetravalent actinides (Np and Pu) compared with hexavalent uranium. Thus, the use of AHA offers a route for controlling neptunium and plutonium in the UREX process by complexant based stripping of Np(IV) and Pu(IV) from the TBP solvent phase, while U(VI) ions are not affected by AHA and remain solvated in the TBP phase. In the European GANEX process, AHA is also used to form hydrophilic complexes with actinides and strip them from the organic phase into nitric acid. However, AHA does not decompose completely when treated with nitric acid and hampers nitric acid recycling. In lieu of using AHA in the UREX + process, formohydroxamic acid (FHA), although not commercially available, hold promises as a replacement for AHA. FHA undergoes hydrolysis to formic acid which is volatile, thus allowing the recycling of nitric acid. Unfortunately, FHA powder was not stable in the experiments we ran in our laboratory. In addition, AHA and FHA also decompose to hydroxylamine which may undergo an autocatalytic reaction. Other reductants are available and could be extremely useful for actinides separation. The review presents the current plutonium reductants used in used nuclear fuel reprocessing and will introduce innovative and novel reductants that could become reducers for future research on UNF separation.

Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate

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ISBN 13 :
Total Pages : 27 pages
Book Rating : 4.:/5 (845 download)

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Book Synopsis Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate by : J. Malvyn McKibben

Download or read book Plutonium-uranium Separation in the Purex Process Using Mixtures of Hydroxylamine Nitrate and Ferrous Sulfamate written by J. Malvyn McKibben and published by . This book was released on 1983 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Purex Process for Plutonium and Uranium Recovery

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (953 download)

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Book Synopsis Purex Process for Plutonium and Uranium Recovery by :

Download or read book Purex Process for Plutonium and Uranium Recovery written by and published by . This book was released on 1949 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.).

Study of Uranium, IV, Nitrate as Reductant for Plutonium

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Total Pages : pages
Book Rating : 4.:/5 (636 download)

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Book Synopsis Study of Uranium, IV, Nitrate as Reductant for Plutonium by : E. Lopez-Menchero

Download or read book Study of Uranium, IV, Nitrate as Reductant for Plutonium written by E. Lopez-Menchero and published by . This book was released on 1966 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Science Abstracts

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ISBN 13 :
Total Pages : 900 pages
Book Rating : 4.0/5 ( download)

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Book Synopsis Nuclear Science Abstracts by :

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 900 pages. Available in PDF, EPUB and Kindle. Book excerpt: NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Photochemical Technique for Reduction of Uranium and Subsequently Plutonium in the Purex Process

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Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Photochemical Technique for Reduction of Uranium and Subsequently Plutonium in the Purex Process by :

Download or read book Photochemical Technique for Reduction of Uranium and Subsequently Plutonium in the Purex Process written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A photochemical modification of the Purex process is described in which a purified side stream of UO2/sup + +/ ion is reduced to U/sup +4/ outside the radioactive area of the reprocessing plant. The U/sup +4/ is then cycled back to step 2 of the Purex process to reduce the plutonium and effect separation within the partitioning column. This process is shown to be very energy efficient and compatible with existing conventional lamp technology. Preliminary cost estimates of the energy requirements for photon production are essentially negligible. Conceptual systems and photochemical reactor designs are presented. Potential benefits of this system are discussed.