Analysis of Cladding Residues from the Dissolution of Irradiated Dresden-1 Reactor Fuel

PDF Version Also Available for Download.

Description

The primary goal of this work was to evaluate the efficacy of the chop-leach spent fuel dissolution process, with nitric acid dissolvent, for removing actinides and fission products from Zircaloy cladding to produce a cladding capable of meeting low-level waste (LLW) disposal criteria. Analysis of the cladding shows that actinides are present in the cladding at concentrations 50 to 400 times greater than the acceptable TRU limit in LLW. It appears that the nitric acid used for dissolution (initial concentration 4 M, with 10 M added as the dissolution proceeded) was inadequate for solubilizing the fuel meat. Scanning electron micrographs ... continued below

Physical Description

vp.

Creation Information

KESSINGER, GF. May 27, 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.

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

The primary goal of this work was to evaluate the efficacy of the chop-leach spent fuel dissolution process, with nitric acid dissolvent, for removing actinides and fission products from Zircaloy cladding to produce a cladding capable of meeting low-level waste (LLW) disposal criteria. Analysis of the cladding shows that actinides are present in the cladding at concentrations 50 to 400 times greater than the acceptable TRU limit in LLW. It appears that the nitric acid used for dissolution (initial concentration 4 M, with 10 M added as the dissolution proceeded) was inadequate for solubilizing the fuel meat. Scanning electron micrographs of the as-sampled cladding surface showed particles of material high in U on the surface of the cut samples, suggesting the fuel meat was not completely dissolved. If the cladding is to meet LLW disposal limits, it is likely that a more robust chemical treatment will be required to more completely digest the fuel meat. Based on the available analytical results, and the interpretation of those results, the following conclusions are drawn. The chop-leach method, as performed initially was inadequate for complete digestion of the fuel meat present in the Dresden-1 fuel samples studied. This failure of the dissolution process resulted in cladding samples that contained TRU actinides about 400 times more TRU content than is allowable in LLW. The inductively-coupled plasma emission spectroscopy (ICP-ES) method appears to overestimate the quantities of a variety of elements, such as Ag, Ce, Gd, La, and Sb. It is believed this phenomenon is related to spectral interferences from d-block and f-block elements. Future studies should be performed to determine the efficacy of leaching to chemically polish the cladding surface and remove undissolved fuel meat. Further analyses of cladding samples, to more thoroughly characterize the nature of the U- and TRU-bearing phases present in the cladding, are recommended.

Physical Description

vp.

Source

  • Other Information: PBD: 27 May 2004

Language

Item Type

Identifier

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

  • Report No.: WSRC-TR-2004-00178
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/824781 | External Link
  • Office of Scientific & Technical Information Report Number: 824781
  • Archival Resource Key: ark:/67531/metadc783470

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

  • May 27, 2004

Added to The UNT Digital Library

  • Dec. 3, 2015, 9:30 a.m.

Description Last Updated

  • May 4, 2016, 9:22 p.m.

Usage Statistics

When was this report last used?

Yesterday: 0
Past 30 days: 0
Total Uses: 9

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

KESSINGER, GF. Analysis of Cladding Residues from the Dissolution of Irradiated Dresden-1 Reactor Fuel, report, May 27, 2004; South Carolina. (digital.library.unt.edu/ark:/67531/metadc783470/: accessed May 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.