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Solvent Extraction of Uranium and Plutonium Without Use of a Salting Out Agent

Solvent Extraction of Uranium and Plutonium Without Use of a Salting Out Agent PDF Author: L. C. Schwendiman
Publisher:
ISBN:
Category :
Languages : en
Pages : 14

Book Description


Solvent Extraction of Uranium and Plutonium Without Use of a Salting Out Agent

Solvent Extraction of Uranium and Plutonium Without Use of a Salting Out Agent PDF Author: L. C. Schwendiman
Publisher:
ISBN:
Category :
Languages : en
Pages : 14

Book Description


The Purex Process

The Purex Process PDF Author: E. R. Irish
Publisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 72

Book Description


The Use of Tetravalent Uranium and Hydrazine as Partitioning Agents in Solvent Extraction Process for Plutonium and Uranium

The Use of Tetravalent Uranium and Hydrazine as Partitioning Agents in Solvent Extraction Process for Plutonium and Uranium PDF Author: J. S. Buckingham
Publisher:
ISBN:
Category :
Languages : en
Pages : 34

Book Description


Performance of a Plutonium Reflux Solvent Extraction System

Performance of a Plutonium Reflux Solvent Extraction System PDF Author: B. F. Judson
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 30

Book Description


Solvent Extraction Separation of Uranium and Plutonium from Fission Products

Solvent Extraction Separation of Uranium and Plutonium from Fission Products PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14

Book Description
Solvent extraction, with tri-n-butyl phosphate (TBP) as the solvent and nitric acid as the saltine agent, has been utilized as an efficient method for the separation of uranium and plutonium from fission products. A solution of TBP in refined kerosene extracts uranium (VI) and plutonium (IV) from a nitric acid solution of irradiated uranium, leaving the bulk of the fission products in the aqueous phase. The organic phase is then treated successively with fresh nitric acid to remove fission products, with ferrous sulfamate in nitric acid to recover the plutonium which has been reduced to plutonium (III), and finally with water to recover the uranium. At this point the uranium and plutonium have been quantitatively separated from one another. Further decontamination from fission products may be achieved in a second cycle of solvent extraction if required.

Solvent Extraction Principles and Practice, Revised and Expanded

Solvent Extraction Principles and Practice, Revised and Expanded PDF Author: Jan Rydberg
Publisher: CRC Press
ISBN: 0824752201
Category : Science
Languages : en
Pages : 760

Book Description
A complete and up-to-date presentation of the fundamental theoretical principles and many applications of solvent extraction, this enhanced Solvent Extraction Principles and Practice, Second Edition includes new coverage of the recent developments in solvent extraction processes, the use of solvent extraction in analytical applications and waste recovery, and computational chemistry methods for modeling the solvent extraction of metal ions. Offering sound scientific and technical descriptions in a format accessible to students and expedient for researchers and engineers, this edition also features a new chapter on ionic strength corrections and contains more than 850 up-to-date literature citations.

Solvent Extraction of Uranium

Solvent Extraction of Uranium PDF Author:
Publisher:
ISBN:
Category : Solvent extraction
Languages : en
Pages : 24

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1462

Book Description
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.

DI-2-Amyl 2-Butylphosphonate as an Extractant for the Recovery of Uranium and Plutonium

DI-2-Amyl 2-Butylphosphonate as an Extractant for the Recovery of Uranium and Plutonium PDF Author: Thomas H. Siddall
Publisher:
ISBN:
Category : Extraction (Chemistry)
Languages : en
Pages : 20

Book Description


TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 212

Book Description