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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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
U. Kamachi Mudali, A. Ravi Shankar, R. Natarajan, N. Saibaba, Baldev Raj
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 349-357
Technical Paper | Reprocessing/Materials for Nuclear Systems | doi.org/10.13182/NT12-73
Articles are hosted by Taylor and Francis Online.
Zirconium is highly resistant to nitric acid environments and is considered as a candidate material for various applications in spent nuclear fuel reprocessing plants involving concentrated nitric acid medium under highly corrosive oxidizing conditions. Zirconium is insensitive to intergranular corrosion in nitric acid unlike stainless steels of Type AISI 304L (304L SS), which is commonly used in reprocessing plants. Also, unlike titanium and its alloys, zirconium is not affected by the vapor and condensate phases of boiling nitric acid. Zirconium and its alloys are thus considered candidate materials for various applications in spent nuclear fuel reprocessing plants involving nitric acid of high concentrations at high temperatures. This paper discusses the international experience on zirconium for reprocessing plant applications and the consideration of Zircaloy-4 (Zr-4) for reprocessing plant applications based on the research and development work carried out at Indira Gandhi Centre for Atomic Research on Zr-4 as well as manufacturing of dissimilar joints between Zr-4 and 304L SS and a mock-up dissolver for fast breeder reactor reprocessing.