Interactive leach tests of UO/sub 2/ and spent fuel with waste package components in salt brine

PDF Version Also Available for Download.

Description

Spent fuel is being considered as a waste form for disposal in a repository located in salt. To adequately model spent fuel performance as a waste form that may be contacted by brine in a repository, it is necessary to describe the leach (dissolution) behavior of spent fuel and the chemical interactions of the released radionuclides with their environment. To this end, leach tests were conducted on: UO/sub 2/ in Permian Basin salt brine or deionized water at test temperatures of 25, 75, and 150/sup 0/C. Some tests were done in the presence of ductile cast iron, which is a ... continued below

Physical Description

Pages: 82

Creation Information

Barner, J.O.; Gray, W.J.; McVay, G.L. & Shade, J.W. September 1, 1986.

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

Spent fuel is being considered as a waste form for disposal in a repository located in salt. To adequately model spent fuel performance as a waste form that may be contacted by brine in a repository, it is necessary to describe the leach (dissolution) behavior of spent fuel and the chemical interactions of the released radionuclides with their environment. To this end, leach tests were conducted on: UO/sub 2/ in Permian Basin salt brine or deionized water at test temperatures of 25, 75, and 150/sup 0/C. Some tests were done in the presence of ductile cast iron, which is a representative overpack material, and/or oxidized Zircaloy, which is the usual fuel cladding material. Spent fuel (H.B. Robinson) in Permian Basin salt brine at 25 and 75/sup 0/C. Some of the tests were conducted in the presence of ductile cast iron. The release values for leach periods up to 60 days were determined for systems utilizing both UO/sub 2/ and spent fuel. This report is based upon data obtained during 1982 and 1983. The larger temperature dependence of the leach behavior that was observed for deionized water than was observed for brine is difficult to interpret on the basis of our knowledge. Differences in UO/sub 2/ alteration products may be involved. For example, the existence of sodium uranates is likely in the brines but not possible with deionized water. Differences in ionic strength may also play a role. Observations derived from the leach tests performed in brine include: (1) the presence of iron coupons had no effect on total release of uranium from either spent fuel or UO/sub 2/ but did reduce solution concentrations, and (2) 100 to 200 times more uranium was released from spent fuel than from UO/sub 2/ per unit of geometric surface area.

Physical Description

Pages: 82

Notes

NTIS, PC A05/MF A01.

Language

Item Type

Identifier

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

  • Other: DE86016083
  • Report No.: PNL-4898-SRP
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/5348066 | External Link
  • Office of Scientific & Technical Information Report Number: 5348066
  • Archival Resource Key: ark:/67531/metadc1070739

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

  • September 1, 1986

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

Description Last Updated

  • April 20, 2018, 4:33 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 1
Total Uses: 2

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

Barner, J.O.; Gray, W.J.; McVay, G.L. & Shade, J.W. Interactive leach tests of UO/sub 2/ and spent fuel with waste package components in salt brine, report, September 1, 1986; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1070739/: accessed May 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.