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
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.
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
Fusion Science and Technology
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. J. Reilly, L. E. Peters, Jr.
Nuclear Technology | Volume 9 | Number 3 | September 1970 | Pages 356-363
Fuel Cycle | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28790
Articles are hosted by Taylor and Francis Online.
A method was developed for determining the optimum fuel utilization for the Plum Brook Reactor (PBR). The method used available PBR criticality data to incorporate the effects of neutron leakage and nonuniformity of burnup in a point model of the core. This allowed the model to predict the performance of the core as a function of new element weight and number of uses per element. A graphical model was devised to determine the optimum. The article shows the derivation of the model and its application for a typical PBR configuration.
