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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Gustavo A. Cragnolino, Darrell S. Dunn, C. Sean Brossia, Yi-Ming Pan, Osvaldo Pensado, Lietai Yang
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 166-173
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3556
Articles are hosted by Taylor and Francis Online.
The susceptibility to various forms of corrosion that could be experienced by the alloys considered by the U.S. Department of Energy for the waste package and drip shield, the principal components of the engineered barrier system for the proposed repository at Yucca Mountain, is evaluated on the basis of experimental studies conducted at the Center for Nuclear Waste Regulatory Analyses. Environmental, metallurgical, and mechanical conditions for the occurrence of uniform corrosion, localized corrosion, and environmentally assisted cracking of Alloy 22 (58Ni-22Cr-13Mo-3W-4Fe), the preferred material for the outer container, and Titanium-Grade 7 (Ti-0.15 Pd), the alloy proposed for the drip shield, are reported.