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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
CLEAN SMART bill reintroduced in Senate
Senators Ben Ray Luján (D., N.M.) and Tim Scott (R., S.C.) have reintroduced legislation aimed at leveraging the best available science and technology at U.S. national laboratories to support the cleanup of legacy nuclear waste.
The Combining Laboratory Expertise to Accelerate Novel Solutions for Minimizing Accumulated Radioactive Toxins (CLEAN SMART) Act, introduced on February 11, would authorize up to $58 million annually to develop, demonstrate, and deploy innovative technologies, targeting reduced costs and safer, faster remediation of sites from the Manhattan Project and Cold War.
G. P. Rutledge, F. A. Dobbe, C. H. Price
Nuclear Technology | Volume 2 | Number 6 | December 1966 | Pages 461-467
Technical Paper and Note | doi.org/10.13182/NT66-A27537
Articles are hosted by Taylor and Francis Online.
This paper presents calculated values of the extrapolation distance for the water-reflected 235U-H2O-Zr ternary system. This extrapolation distance, together with previously published critical buckling data, permits the ready determination of critical dimensions for all possible compositions of this system. Prior to this study, only limited data were available for the extrapolation distance for the 235U-H2O binary system, and no data existed for the ternary system. A quantitative determination of the extrapolation distance was achieved utilizing, in a unique manner, nuclear codes developed for reactor design purposes. Accuracy of the results has been confirmed at compositions for which experimental data are available. The extrapolation distance was found to be essentially independent of the shape of the system but strongly dependent upon composition. A single diagram that presents critical buckling and extrapolation distance as a function of composition has been developed. With this diagram it is possible to determine critical dimensions for a given shape and composition and optimum conditions for criticality. As an important practical example, the minimum critical limits for optimally water-moderated cylindrical arrays of 235U-Zr fuel elements are presented as a function of fuel-element length and composition.