Author: M.A. MairPublisher:
ISBN: 9780853562306
Category : Plutonium alloys
Languages : en
Pages : 7
Book Description
A method for the separation of americium, uranium and plutonium, in plutonium concentrate solutions
Author: M.A. MairPublisher:
ISBN: 9780853562306
Category : Plutonium alloys
Languages : en
Pages : 7
Book Description
A Method for the Separation of Americium, Uranium Andplutoniumin Plutonium Concentrate Solutions
Author: M. A. MairThe Quantitative Seperation of Americium from Plutonium and Uranium
Author: H. W. MillerPublisher:
ISBN:
Category : Chemistry
Languages : en
Pages : 20
Book Description
Nuclear Wastes
Author: National Research CouncilPublisher: National Academies Press
ISBN: 0309052262
Category : Science
Languages : en
Pages : 590
Book Description
Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
The Quantitative Separation of Americium from Plutonium and Uranium
Author: H. W. MillerPublisher:
ISBN:
Category : Americium
Languages : en
Pages : 16
Book Description
The Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the Truex Process - Continuing Development Studies
Author: R. A. LeonardSeparation and Determination of Plutonium in Plutonium-uranium Fuel Elements
Author: C. E. PietriPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 16
Book Description
Extraction Chromatography
Author: Publisher: Elsevier
ISBN: 0080858023
Category : Science
Languages : en
Pages : 585
Book Description
Extraction Chromatography
Extraction and Recovery of Plutonium and Americium from Nitric Acid Waste Solutions by the TRUEX Process - Continuing Development Studies
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
This report summarizes the work done to date on the application of the TRUEX solvent extraction process for removing and separately recovering plutonium and americium from a nitric acid waste solution containing these elements, uranium, and a complement of inert metal ions. This simulated waste stream is typical of a raffinate from a tributyl phosphate (TBP)-based solvent extraction process for removing uranium and plutonium from dissolved plutonium-containing metallurgical scrap. The TRUEX process solvent in these experiments was a solution of TBP and octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) dissolved in carbon tetrachloride. A flowsheet was designed on the basis of measured batch distribution ratios to reduce the TRU content of the solidified raffinate to less than or equal to 10 nCi/g and was tested in a countercurrent experiment performed in a 14-stage Argonne-model centrifugal contractor. The process solvent was recycled without cleanup. An unexpectedly high evaporative loss of CCl4 resulted in concentration of the active extractant, CMPO, to nearly 0.30M in the solvent. Results are consistent with this higher CMPO concentration. The raffinate contained only 2 nCi/g of TRU, but the higher CMPO concentration resulted in reduced effectiveness in the stripping of americium from the solvent. Conditions can be easily adjusted to give high yields and good separation of americium and plutonium. Experimental studies of the hydrolytic and gamma-radiolytic degradation of the TRUEX-CCl4 showed that solvent degradation would be (1) minimal for a year of processing this typical feed, which contained no fission products, and (2) could be explained almost entirely by hydrolytic and radiolytic damage to TBP. Even for gross amounts of solvent damage, scrubbing with aqueous sodium carbonate solution restored the original americium extraction and stripping capability of the solvent. 43 refs., 5 figs., 36 tabs.
Chemical Aspects of the Precise and Accurate Determination of Uranium and Plutonium from Nuclear Fuel Solutions
Author: Olli J. HeinonenPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 80
Book Description