Uranium Metal Dissolution in the Presence of Fluoride and Boron

PDF Version Also Available for Download.

Description

H-Area Operations is planning to process plutonium-contaminated (Pu-contaminated) uranium metal scrap in its efforts to de-inventory excess nuclear materials. Experimental work was performed with a piece of uranium sheet. The study had four primary objectives. First, gather reaction rate data at a range of processing conditions to compare against reaction rate data reported in earlier studies and recommend a flowsheet for H-Canyon and/or for HB-Line. Second, develop new data for calculating hydrogen and total generation rates during uranium metal dissolution. Third, the tests intend to provide data to help demonstrate that the proposed flowsheet does not pose a criticality hazard. ... continued below

Physical Description

vp.

Creation Information

Pierce, R.A. February 2, 2004.

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.

Author

Sponsor

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

H-Area Operations is planning to process plutonium-contaminated (Pu-contaminated) uranium metal scrap in its efforts to de-inventory excess nuclear materials. Experimental work was performed with a piece of uranium sheet. The study had four primary objectives. First, gather reaction rate data at a range of processing conditions to compare against reaction rate data reported in earlier studies and recommend a flowsheet for H-Canyon and/or for HB-Line. Second, develop new data for calculating hydrogen and total generation rates during uranium metal dissolution. Third, the tests intend to provide data to help demonstrate that the proposed flowsheet does not pose a criticality hazard. Last, use the data to recommend a process flowsheet.

Physical Description

vp.

Source

  • Other Information: PBD: 2 Feb 2004

Language

Item Type

Identifier

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

  • Report No.: WSRC-TR-2003-00500
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/821176 | External Link
  • Office of Scientific & Technical Information Report Number: 821176
  • Archival Resource Key: ark:/67531/metadc739747

Collections

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

Office of Scientific & Technical Information Technical Reports

What responsibilities do I have when using this report?

When

Dates and time periods associated with this report.

Creation Date

  • February 2, 2004

Added to The UNT Digital Library

  • Oct. 18, 2015, 6:40 p.m.

Description Last Updated

  • May 5, 2016, 5:57 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 2

Interact With This Report

Here are some suggestions for what to do next.

Start Reading

PDF Version Also Available for Download.

Citations, Rights, Re-Use

Pierce, R.A. Uranium Metal Dissolution in the Presence of Fluoride and Boron, report, February 2, 2004; South Carolina. (digital.library.unt.edu/ark:/67531/metadc739747/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.