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Researcher
- Radu Custelcean
- Amit Shyam
- Beth L Armstrong
- Peeyush Nandwana
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- Wei Zhang
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- Yousub Lee
- Yutai Kato
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- Jiheon Jun
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- Jovid Rakhmonov
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- Laetitia H Delmau
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- Thomas R Muth
- Tim Graening Seibert
- Tolga Aytug
- Trevor Aguirre
- Uvinduni Premadasa
- Venugopal K Varma
- Vera Bocharova
- Weicheng Zhong
- Wei Tang
- William Peter
- Xiang Chen
- Yan-Ru Lin
- Yingzhong Ma
- Yiyu Wang
- Yukinori Yamamoto

The invention teaches a method for separating uranium and the transuranic actinides neptunium, plutonium, and americium from nitric acid solutions by co-crystallization upon lowering the temperature from 60 C to 20 C or lower.

A finite element approach integrated with a novel constitute model to predict phase change, residual stresses and part deformation.

The technologies provides for regeneration of anion-exchange resin.
Contact
To learn more about this technology, email partnerships@ornl.gov or call 865-574-1051.

Ruthenium is recovered from used nuclear fuel in an oxidizing environment by depositing the volatile RuO4 species onto a polymeric substrate.

Currently available cast Al alloys are not suitable for various high-performance conductor applications, such as rotor, inverter, windings, busbar, heat exchangers/sinks, etc.

The invented alloys are a new family of Al-Mg alloys. This new family of Al-based alloys demonstrate an excellent ductility (10 ± 2 % elongation) despite the high content of impurities commonly observed in recycled aluminum.

This invention describes a new class of amphiphilic chelators (extractants) that can selectively separate large, light rare earth elements from heavy, small rare earth elements in solvent extraction schemes.

A pressure burst feature has been designed and demonstrated for relieving potentially hazardous excess pressure within irradiation capsules used in the ORNL High Flux Isotope Reactor (HFIR).

Among the methods for point source carbon capture, the absorption of CO2 using aqueous amines (namely MEA) from the post-combustion gas stream is currently considered the most promising.

V-Cr-Ti alloys have been proposed as candidate structural materials in fusion reactor blanket concepts with operation temperatures greater than that for reduced activation ferritic martensitic steels (RAFMs).