NDLI: Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution

Content Provider	Springer Nature Link
Author	Delegard, C. H. Sinkov, S. I. Chenault, J. W. Schmidt, A. J. Welsh, T. L. Pool, K. N.
Copyright Year	2013
Abstract	Irradiated uranium metal fuel was stored underwater in the K East and K West storage basins at the US Department of Energy Hanford Site. The uranium metal under damaged cladding reacted with water to generate hydrogen gas, uranium oxides, and spalled uranium metal particles which intermingled with other particulates to form sludge. While the fuel has been removed, uranium metal in the sludge remains hazardous. An expeditious routine method to analyze 0.03 wt% uranium metal in the presence of >30 wt% total uranium was needed to support safe sludge management and processing. A selective dissolution method was designed based on the rapid uranium oxide dissolution but very low uranium metal corrosion rates in hot concentrated phosphoric acid. The uranium metal-bearing heel from the phosphoric acid step then is rinsed before the uranium metal is dissolved in hot concentrated nitric acid for analysis. Technical underpinnings of the selective dissolution method, including the influence of sludge components, were investigated to design the steps and define the reagents, quantities, concentrations, temperatures, and times within the selective dissolution analysis. Tests with simulant sludge proved the technique feasible. Tests with genuine sludge showed a 0.0028 ± 0.0037 wt% (at one standard deviation) uranium metal analytical background, a 0.011 wt% detection limit, and a 0.030 wt% quantitation limit in settled (wet) sludge. In tests using genuine K Basin sludge spiked with uranium metal at concentrations above the 0.030 wt% ± 25 % (relative) quantitation limit, uranium metal recoveries averaged 99.5 % with a relative standard deviation of 3.5 %.
Starting Page	1871
Ending Page	1882
Page Count	12
File Format	PDF
ISSN	02365731
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume Number	299
Issue Number	3
e-ISSN	15882780
Language	English
Publisher	Springer Netherlands
Publisher Date	2013-12-17
Publisher Place	Dordrecht
Access Restriction	One Nation One Subscription (ONOS)
Subject Keyword	Uranium metal Uranium oxides Nuclear fuel storage basin sludge Phosphoric acid Nuclear Chemistry Physical Chemistry Nuclear Physics, Heavy Ions, Hadrons Diagnostic Radiology Inorganic Chemistry
Content Type	Text
Resource Type	Article
Subject	Spectroscopy Pollution Health, Toxicology and Mutagenesis Radiology, Nuclear Medicine and Imaging Analytical Chemistry Public Health, Environmental and Occupational Health Nuclear Energy and Engineering

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

A study of nitrogen oxides released into the gas phase during uranium nitride dissolution in nitric acid

Determination of uranium in phosphoric acid using neutron activation analysis

Dissolution of uranium oxides under alkaline oxidizing conditions

Dissolution of uranium oxides from simulated environmental swipes using ammonium bifluoride

Determination of oxygen to uranium ratio in irradiated uranium dioxide by controlled potential coulometry

Phosphoric acid as uranium complexant in kinetic phosphorimetry

A quick method to determine uranium concentration by gamma spectroscopy: Its application for extraction of uranium from wet phosphoric acid

A new method for alkaline dissolution of uranium metal foil

Determination of hexavalent and tetravalent uranium in phosphate ores through hydrochloric acid selective leaching

Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution

Similar Documents

A study of nitrogen oxides released into the gas phase during uranium nitride dissolution in nitric acid

Determination of uranium in phosphoric acid using neutron activation analysis

Dissolution of uranium oxides under alkaline oxidizing conditions

Dissolution of uranium oxides from simulated environmental swipes using ammonium bifluoride

Determination of oxygen to uranium ratio in irradiated uranium dioxide by controlled potential coulometry

Phosphoric acid as uranium complexant in kinetic phosphorimetry

A quick method to determine uranium concentration by gamma spectroscopy: Its application for extraction of uranium from wet phosphoric acid

A new method for alkaline dissolution of uranium metal foil

Determination of hexavalent and tetravalent uranium in phosphate ores through hydrochloric acid selective leaching

Determination of uranium metal concentration in irradiated fuel storage basin sludge using selective dissolution