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Title: Characterization of undissolved solids from the dissolution of North Anna reactor fuel

Here, samples of undissolved solids (UDS) from the dissolution of North Anna reactor fuel were characterized to investigate the effects of using air or oxygen as the oxidant during tritium removal. The UDS composition data also support the development of a waste form for disposal. There was no discernible effect of the oxidant used during the tritium removal process or the size fraction on the UDS composition. Scanning electron microscopy (SEM) and energy dispersive (x-ray) spectroscopy were used to estimate the oxygen content of the UDS and it was found to be potentially significant, on the order of 30% by mass and 80% by atom.
Authors:
 [1] ;  [1] ;  [1]
  1. Savannah River National Lab., Aiken, SC (United States)
Publication Date:
Report Number(s):
SRNL-STI-2016-00523
Journal ID: ISSN 0149-6395
Grant/Contract Number:
AC09-08SR22470
Type:
Accepted Manuscript
Journal Name:
Separation Science and Technology
Additional Journal Information:
Journal Name: Separation Science and Technology; Journal ID: ISSN 0149-6395
Publisher:
Taylor & Francis
Research Org:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; Tritium removal process; undissolved solids characterization; used nuclear fuel dissolution
OSTI Identifier:
1439433