ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
R. H. Augustson, C. N. Henry, C. R. Weisbin
Nuclear Technology | Volume 14 | Number 2 | May 1972 | Pages 197-199
Technical Note | Analysis | doi.org/10.13182/NT72-A31136
Articles are hosted by Taylor and Francis Online.
The 235U content of a spent MTR fuel element enclosed in a lead transfer cask has been nondestructively measured by observing the delayed-neutron emissions following high energy neutron induced fission. Fourteen MeV neutrons from a (D,T) neutron generator moderated through 8 in. of lead were used as the interrogating radiation. A DTF-IV calculation was used to correct the data for the contributions due to other fissionable isotopes. The nondestructive measurement agreed to within 1.5% with the 235U content as predicted by reactor burnup calculations.
