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 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
X-energy raises $700M in latest funding round
Advanced reactor developer X-energy has announced that it has closed an oversubscribed Series D financing round of approximately $700 million. The funding proceeds are expected to be used to help continue the expansion of its supply chain and the commercial pipeline for its Xe-100 advanced small modular reactor and TRISO-X fuel, according the company.
P. Grillo, G. Testa
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 130-139
Technical Paper and Note | doi.org/10.13182/NT68-A28042
Articles are hosted by Taylor and Francis Online.
Hot spot factors due to fissile material segregation in UO2-PuO2 fuels and to geometrical tolerances in the fuel rods are calculated for both vibrationally compacted and pelleted fuels to produce optimum design for light-water reactors. Neutron flux distribution in the fuel is calculated using the transport theory, while the trend of the heat flux transferred to the coolant is evaluated by a three-dimensional heat-transfer code. Segregation of fissile material is significant for vibrationally compacted fuel, and appears negligible for pelleted fuel. The geometrical tolerances considered give values for engineering hot channel factors that are quite relevant for fuel-rod design.
