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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Nuclear Science and Engineering
June 2025
Nuclear Technology
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
H. L. Adair, E. H. Kobisk
Nuclear Technology | Volume 25 | Number 2 | February 1975 | Pages 224-236
Technical Paper | Material Dosimetry | doi.org/10.13182/NT75-A24365
Articles are hosted by Taylor and Francis Online.
The Isotopes Division of Oak Ridge National Laboratory has developed procedures for providing accurately defined deposits of 239 PuO2 and 235 UO2 for use in precision neutron cross-section measurements. Encapsulated samples of 6Li, 10B, 45Sc, 232Th, 235U, 238 U, 237Np, 238Pu, 239Pu, and 241 Pu for use as neutron monitors in reactors can also be provided. These dosimeters are used to determine integral reaction rates from which the neutron energy spectrum, flux, and fluence at particular locations within a reactor can be computed. Methods for the preparation and characterization of reactor dosimeters and other reaction rate samples provide an accuracy of ≤±1% at the 95% confidence level (CL).
