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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
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.