D.W. Simmons

Oak Ridge National Laboratory — United States

Engineering · Physical Sciences

4h-index47citations27works0.02yr avg
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Research Topics

Nuclear and radioactivity studies(10), Graphite, nuclear technology, radiation studies(8), Nuclear reactor physics and engineering(7), Radioactive element chemistry and processing(5), Nuclear Materials and Properties(5)

Publications27 total

Investigating the hydrolysis of cryogenically layered molybdenum hexafluoride through a disordered hydrogen-bonded network
Physical Chemistry Chemical Physics·2022· 7 citedOpen Access
Use of an Infrared Spectroscopic Method for Isotopic Analysis of Gaseous Uranium Hexafluoride
˜The œminerals, metals & materials series·2021· 1 cited
Infrared spectroscopic method for uranium isotopic analysis
2020· 3 cited
Design of Fieldable Head Space Manifold
2019· 1 citedOpen Access
On Line Enrichment Monitor (OLEM) UF<sub>6</sub> Tests for 1.5" Sch40 SS Pipe, Revision 1
2016· 2 citedOpen Access
Laboratory-Scale UF6 Test Bed Supporting Nonproliferation Research and Development
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)·2012Open Access
A Miniature Self-Contained CdZnTe Gamma Spectrometer for Use in Unattended Nuclear Material Monitoring
2006
Investigation of the Chemical Reactivity of Phosgene in Uranium Hexafluoride
2006
The ORNL plasma fueling program
2003· 2 cited
Development of the Process for the Recovery and Conversion of<sup>233</sup>UF<sub>6</sub>Chemisorbed in NaF Traps from the Molten Salt Reactor Remediation Project
Nuclear Technology·2001
Overview of the recovery and processing of {sup 233}U from the Oak Ridge molten salt reactor experiment (MSRE) remediation activities
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)·2001
Prototype Tests for the Recovery and Conversion of UF6 Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project
2000· 4 citedOpen Access
Prototype Tests for the Recovery and Conversion of UF6 Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project
2000· 1 citedOpen Access
Some Investigations of the Reaction of Activated Charcoal with Fluorine and Uranium Hexafluoride
1998· 3 citedOpen Access
Passivation of fluorinated activated charcoal
1997· 3 citedOpen Access
Laboratory tests using chlorine trifluoride in support of deposit removal at MSRE
1997· 1 citedOpen Access
An introduction to technetium in the gaseous diffusion cascades
1996· 7 citedOpen Access
Evaluation of gas-phase technetium decontamination and safety related experiments during FY 1994. A report of work in progress
1995· 3 citedOpen Access
The Stability of CI02 as a Product of Gas Phase Decontamination Treatments
1994Open Access
Off-gas recycle for long-term low temperature gas phase uranium decontamination
University of North Texas Digital Library (University of North Texas)·1994Open Access
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Frequent Co-authors

G. D. Del Cul(7), L.D. Trowbridge(7), S. L. Milora(5), S. K. Combs(5), C. R. Foust(5), E.B. Munday(4), A.S. Icenhour(4), L.M. Toth(4), C.A. Foster(4), K. Alicia Strange Fessler(3), D. F. Williams(3), M.J. Gouge(3), P.W. Fisher(3), C. C. Tsai(3), B.E. Argo(3), D. T. Fehling(3), D. E. Schechter(3), D. O. Sparks(3), Patrick E. O’Rourke(2), Nicholas DeRoller(2)