Mac R. Zumhoff
Pacific Northwest National Laboratory
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Featured researches published by Mac R. Zumhoff.
Applied Physics Letters | 2002
Michael S. Weaver; Lech Michalski; Kamala Rajan; Mark A. Rothman; Jeffrey Silvernail; Julie J. Brown; Paul E. Burrows; Gordon L. Graff; Mark E. Gross; Peter M. Martin; Michael G. Hall; Charles C. Bonham; Wendy D. Bennett; Mac R. Zumhoff
We fabricate long-lived organic light-emitting devices using a 175 μm thick polyethylene terephthalate substrate coated with an organic–inorganic multilayered barrier film and compare the rate of degradation to glass-based devices. The observed permeation rate of water vapor through the plastic substrate was estimated to be 2×10−6 g/m2/day. Driven at 2.5 mA/cm2, we measure a device lifetime of 3800 h from an initial luminance of 425 cd/m2.
Archive | 2010
Denis M. Strachan; Jarrod V. Crum; Edgar C. Buck; Brian J. Riley; Mac R. Zumhoff
Epsilon metal (e-metal) is generated in nuclear fuel during irradiation. This metal consists of Pd, Ru, Rh, Mo, and some Te. These accumulate at the UO2 grain boundaries as small (ca 5 µm) particles. These metals have limited solubility in the acid used to dissolve fuel during reprocessing and in typical borosilicate glass. These must be treated separately to improve overall waste loading in glass. This low solubility and their survival in 2 Gy-old natural reactors led us to investigate them as a waste form for the immobilization of 99Tc and 107Pd, two very long-lived isotopes.
Archive | 2012
Jarrod V. Crum; Denis M. Strachan; Mac R. Zumhoff
During irradiation of nuclear fuel in a reactor, the five metals, Mo, Pd, Rh, Ru, and Tc, migrate to the fuel grain boundaries and form small metal particles of an alloy known as epsilon metal ({var_epsilon}-metal). When the fuel is dissolved in a reprocessing plant, these metal particles remain behind with a residue - the undissolved solids (UDS). Some of these same metals that comprise this alloy that have not formed the alloy are dissolved into the aqueous stream. These metals limit the waste loading for a borosilicate glass that is being developed for the reprocessing wastes. Epsilon metal is being developed as a waste form for the noble metals from a number of waste streams in the aqueous reprocessing of used nuclear fuel (UNF) - (1) the {var_epsilon}-metal from the UDS, (2) soluble Tc (ion-exchanged), and (3) soluble noble metals (TRUEX raffinate). Separate immobilization of these metals has benefits other than allowing an increase in the glass waste loading. These materials are quite resistant to dissolution (corrosion) as evidenced by the fact that they survive the chemically aggressive conditions in the fuel dissolver. Remnants of {var_epsilon}-metal particles have survived in the geologically natural reactors found in Gabon, Africa, indicating that they have sufficient durability to survive for {approx} 2.5 billion years in a reducing geologic environment. Additionally, the {var_epsilon}-metal can be made without additives and incorporate sufficient foreign material (oxides) that are also present in the UDS. Although {var_epsilon}-metal is found in fuel and Gabon as small particles ({approx}10 {micro}m in diameter) and has survived intact, an ideal waste form is one in which the surface area is minimized. Therefore, the main effort in developing {var_epsilon}-metal as a waste form is to develop a process to consolidate the particles into a monolith. Individually, these metals have high melting points (2617 C for Mo to 1552 C for Pd) and the alloy is expected to have a high melting point as well, perhaps exceeding 1500 C. The purpose of the work reported here is to find a potential commercial process with which {var_epsilon}-metal plus other components of UDS can be consolidated into a solid with minimum surface area and high strength Here, we report the results from the preliminary evaluation of spark-plasma sintering (SPS), hot-isostatic pressing (HIP), and microwave sintering (MS). Since bulk {var_epsilon}-metal is not available and companies could not handle radioactive materials, we prepared mixtures of the five individual metal powders (Mo, Ru, Rh, Pd, and Re) and baddeleyite (ZrO{sub 2}) to send the vendors of SPS, HIP, and MS. The processed samples were then evaluated at the Pacific Northwest National Laboratory (PNNL) for bulk density and phase assemblage with X-ray diffraction (XRD) and phase composition with scanning electron microscopy (SEM). Physical strength was evaluated qualitatively. Results of these scoping tests showed that fully dense cermet (ceramic-metal composite) materials with up to 35 mass% of ZrO{sub 2} were produced with SPS and HIP. Bulk density of the SPS samples ranged from 87 to 98% of theoretical density, while HIP samples ranged from 96 to 100% of theoretical density. Microwave sintered samples containing ZrO{sub 2} had low densities of 55 to 60% of theoretical density. Structurally, the cermet samples showed that the individual metals alloyed in to {var_epsilon}-phase - hexagonal-close-packed (HCP) alloy (4-95 mass %), the {alpha}-phase - face-centered-cubic (FCC) alloy structure (3-86 mass %), while ZrO{sub 2} remained in the monoclinic structure of baddeleyite. Elementally, the samples appeared to have nearly uniform composition, but with some areas rich in Mo and Re, the two components with the highest melting points. The homogeneity in distribution of the elements in the alloy is significantly improved in the presence of ZrO{sub 2}. However, ZrO{sub 2} does not appear to react with the alloy, nor was Zr found in the alloy.
Cockpit Displays IX: Displays for Defense Applications | 2002
Michael S. Weaver; Anna B. Chwang; Mark A. Rothman; Jeff Silvernail; Michael Hack; Julie J. Brown; Paul E. Burrows; Gordon L. Graff; Mark E. Gross; Peter M. Martin; Michael G. Hall; Charles C. Bonham; Wendy D. Bennett; Mac R. Zumhoff
Organic light emitting diodes (OLEDs) have recently entered the market place as a competitive flat panel display technology. OLED displays are moving rapidly from small passive matrices (i.e. <3 inches diagonal) to full color active matrices based on rigid substrates. This paper is focused on new developments to help enable flexible OLED (FOLED) displays. Presented here will be high efficiency phosphorescent OLED displays that can be used in either passive or active matrix drive configurations. Passive matrix displays incorporating this technology fabricated on flexible substrates are also reported. These early demonstrations of flexible OLED displays illustrate the promise for a whole new generation of display products based on the design dimension of flexibility.
Archive | 2003
Gordon L. Graff; Mark E. Gross; Wendy D. Bennett; Michael G. Hall; Peter M. Martin; John Chris Pagano; Nicole Rutherford; Mac R. Zumhoff
Archive | 2006
Lorenza Moro; Chu Xi; Martin Philip Rosenblum; Kenneth Jeffrey Nelson; Paul E. Burrows; Mark E. Gross; Mac R. Zumhoff; Peter M. Martin; Charles C. Bonham; Gordon L. Graff
Archive | 2006
Lorenza Moro; Xi Chu; Martin Philip Rosenblum; Kenneth Jeffrey Nelson; Paul E. Burrows; Mark E. Gross; Mac R. Zumhoff; Peter M. Martin; Charles C. Bonham; Gordon L. Graff
Journal of Nuclear Materials | 2013
Jarrod V. Crum; Denis M. Strachan; Aashish Rohatgi; Mac R. Zumhoff
Journal of Nuclear Materials | 2016
Josef Matyas; Nathan L. Canfield; Sannoh Sulaiman; Mac R. Zumhoff
Archive | 2011
Denis M. Strachan; Jarrod V. Crum; Mac R. Zumhoff; Chase C. Bovaird; Charles F. Windisch; Brian J. Riley