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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
R. C. Liikala, V. O. Uotinen, U. P. Jenquin
Nuclear Technology | Volume 15 | Number 2 | August 1972 | Pages 272-296
Technical Paper | Plutonium Utilization in Commercial Power Reactors / Reactor | doi.org/10.13182/NT72-A31151
Articles are hosted by Taylor and Francis Online.
A theoretical analysis of UO2-PuO2 fueled, light water moderated lattice experiments has been performed to aid in establishing technical bases and design criteria for the utilization of plutonium-bearing fuel in thermal power reactors. Results for UO2 and Al-Pu lattices are included to understand the effects due to uranium and plutonium separately. The problems involved in calculating critical experiments are discussed. Estimates of the effects of various approximations inherent in the theoretical methods and/or analysis procedures are included along with the consequence on the results of the correlation. Uncertainties in the measurements and the neutron cross-section data are related to uncertainties in the calculated values of keff. Areas which should be investigated in future analyses are also identified.
