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Nuclear Criticality Safety
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Fusion Science and Technology
Latest News
West Valley completes teardown of Mail Plant Process Building
The Department of Energy’s Office of Environmental Management and its cleanup contractor CH2M Hill BWXT West Valley (CHBWV) completed the on-time removal of the Main Plant Process Building at the West Valley Demonstration Project (WVDP) in New York. Located 35 miles south of Buffalo, the 150-acre WVDP site is home to the only commercial spent nuclear fuel reprocessing facility to operate in the United States.
Gregory C. Staack, Mark L. Crowder, James E. Klein
Fusion Science and Technology | Volume 67 | Number 3 | April 2015 | Pages 580-583
Proceedings of TRITIUM 2013 | doi.org/10.13182/FST14-T84
Articles are hosted by Taylor and Francis Online.
Recently, the demand for He-3 has increased dramatically due to widespread use in nuclear nonproliferation, cryogenic, and medical applications. Essentially all of the world’s supply of He-3 is created by the radiolytic decay of tritium. The Savannah River Site Tritium Facilities (SRS-TF) utilizes LANA.75 in the tritium process to store hydrogen isotopes. The vast majority of He-3 “born” from tritium stored in LANA.75 is trapped in the hydride metal matrix. The SRS-TF has multiple LANA.75 tritium storage beds that have been retired from service with significant quantities of He-3 trapped in the metal. To support He-3 recovery, the Savannah River National Laboratory (SRNL) conducted thermogravimetric analysis coupled with mass spectrometry (TGA-MS) on a tritium aged LANA.75 sample. TGA-MS testing was performed in an argon environment. Prior to testing, the sample was isotopically exchanged with deuterium to reduce residual tritium and passivated with air to alleviate pyrophoric concerns associated with handling the material outside of an inert glovebox. Analyses indicated that gas release from this sample was bimodal, with peaks near 220 and 490°C. The first peak consisted of both He-3 and residual hydrogen isotopes, the second was primarily He-3. The bulk of the gas was released by 600 °C.