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

Journal Article · Fri Jun 16 00:00:00 EDT 2017 · Separation Science and Technology

DOI:https://doi.org/10.1080/01496395.2017.1288138· OSTI ID:1439433

Rudisill, Tracy S. ^[1]; Olson, L. C. ^[1]; DiPrete, D. P. ^[1]

---

1. Savannah River National Lab., Aiken, SC (United States)

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.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC09-08SR22470
• OSTI ID: 1439433
• Report Number(s): SRNL-STI-2016-00523; TRN: US1900612
• Journal Information: Separation Science and Technology, Vol. 53, Issue 12; ISSN 0149-6395
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
Tritium removal process
undissolved solids characterization
used nuclear fuel dissolution