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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
R. C. Lloyd, S. R. Bierman, E. D. Clayton, B. M. Durst
Nuclear Technology | Volume 37 | Number 2 | February 1978 | Pages 148-158
Technical Paper | Plant Water Chemistry / Radioisotope | doi.org/10.13182/NT78-A31982
Articles are hosted by Taylor and Francis Online.
Critical experiments were performed on an annular assembly of 93,2 wt% 235U enriched U-Al alloy fuel elements in light water to provide data for the design and operation of a subcritical neutron multiplier of a 252Cf neutron source. The various factors affecting criticality were determined. In addition to measurement of the critical fuel rod loading under various conditions, values of /ceff were determined as a function of fuel rod loading by means of pulsed neutron source experiments. The data provide the design basis for operation of the neutron multiplier, yielding a maximum flux value in the internal irradiation column consistent with maintaining a degree of subcriticality in operation.
