ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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June 2025
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May 2025
Latest News
Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
C. E. Bemis, Jr., R. E. Druschel, J. Halperin, J. R. Walton
Nuclear Science and Engineering | Volume 47 | Number 3 | March 1972 | Pages 371-372
Technical Note | doi.org/10.13182/NSE72-A22423
Articles are hosted by Taylor and Francis Online.
The thermal-neutron capture cross section and capture resonance integral for 10.7-year 85Kr have been determined in carefully monitored experiments using 99.992% isotopically pure 85Kr. Values of 1.66 ± 0.20 b and 1.8 ± 1.0 b for the thermal-neutron cross section and resonance integral, respectively, were derived from the increase in 86Kr produced during the irradiation and measured mass spectro-metrically. We conclude from our results that the burnup of radioactive 85Kr in power reactors as a possible means of disposal is not feasible.
