RECENT DEVELOPMENTS IN FEED PREPARATION AND SOLVENT EXTRACTION

PDF Version Also Available for Download.

Description

For presentation at the 5th Nuclear Congress, Clevelands Apr. 7, 1959. Increasing emphasis has been placed recently on the application of solvent extraction to the recovery of uranium and plutonium from spent power reactor fuels. Zircaloy-2 jackets were removed from PWR blankettype fuels by dissolution with the Zirflex Process, and the UO/sub 2/ cores were dissolved in 10 M HNO/sub 3/. Zirflex treatment of prototype samples irradiated to 2500 Mwd/ ton resulted in satisfactory dissolution rates and losses to the dejacketing solution generally less than 0.2% for U and Pu. U-Zr alloy fuels were dissolved in 6 M NH/sub 4/F ... continued below

Creation Information

Bruce, F.R.; Blanco, R.E. & Bresee, J.C. March 20, 1959.

Context

This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

Who

People and organizations associated with either the creation of this report or its content.

Publisher

Provided By

UNT Libraries Government Documents Department

Serving as both a federal and a state depository library, the UNT Libraries Government Documents Department maintains millions of items in a variety of formats. The department is a member of the FDLP Content Partnerships Program and an Affiliated Archive of the National Archives.

Contact Us

What

Descriptive information to help identify this report. Follow the links below to find similar items on the Digital Library.

Description

For presentation at the 5th Nuclear Congress, Clevelands Apr. 7, 1959. Increasing emphasis has been placed recently on the application of solvent extraction to the recovery of uranium and plutonium from spent power reactor fuels. Zircaloy-2 jackets were removed from PWR blankettype fuels by dissolution with the Zirflex Process, and the UO/sub 2/ cores were dissolved in 10 M HNO/sub 3/. Zirflex treatment of prototype samples irradiated to 2500 Mwd/ ton resulted in satisfactory dissolution rates and losses to the dejacketing solution generally less than 0.2% for U and Pu. U-Zr alloy fuels were dissolved in 6 M NH/sub 4/F and adjusted for solvent extraction by the addition of ride was recycled by metathesis and precipitation. Stainless steel jackets were removed from Consolidated Edisontype fuels by dissolution in 6 M H/sub 2/SO/sub 4/ (Sulfex Process), and the ThO/sub 2/-UO/sub 2/ core was dissolved in 13 M HNO/sub 3/0.04 M F-0.04 M Al. Dejacketing losses in unirradiated samples were about 0.02%. Use of the ORNL Reference Darex flowsheet for APPR processing resulted in solvent extraction feed containing 30 ppm chloride. Mechanical equipment was designed to declad SRE fuels and chop and leach techniques are being developed to treat stainless and Zr clad ceramic fuel. A solvent extraction flowsheet was developed for Foreign Research Reactor Fuels, (Al-20% enriched U alloy) using a revised tributyl phosphate extraction system for the separation of Pu from U. Feasibility tests were carried out on the coupling of Redox solvent extraction with Darex and Niflex head-end treatments. New solvents for the reprocessing of power reactor fuels are being studied. Among these, the amines show an order of magnitude greater radiation stability than does tributyl phosphate. A primary amine was proposed for the recovery of U and Pu from Sulfex decladding wastes. (auth)

Notes

NTIS

Source

  • Other Information: For presentation at the 5th Nuclear Congress, Cleveland, Apr. 7, 1959. Orig. Receipt Date: 31-DEC-59

Language

Item Type

Identifier

Unique identifying numbers for this report in the Digital Library or other systems.

  • Report No.: CF-58-11-91
  • Grant Number: W-7405-ENG-26
  • DOI: 10.2172/4245829 | External Link
  • Office of Scientific & Technical Information Report Number: 4245829
  • Archival Resource Key: ark:/67531/metadc1026049

Collections

This report is part of the following collection of related materials.

Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • March 20, 1959

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

Description Last Updated

  • Oct. 20, 2017, 2:44 p.m.

Usage Statistics

When was this report last used?

Congratulations! It looks like you are the first person to view this item online.

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

International Image Interoperability Framework

IIF Logo

We support the IIIF Presentation API

Bruce, F.R.; Blanco, R.E. & Bresee, J.C. RECENT DEVELOPMENTS IN FEED PREPARATION AND SOLVENT EXTRACTION, report, March 20, 1959; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc1026049/: accessed June 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.