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.
David G. Martin
Nuclear Technology | Volume 42 | Number 3 | March 1979 | Pages 304-311
Technical Paper | Fuel | doi.org/10.13182/NT79-A32184
Articles are hosted by Taylor and Francis Online.
The fact that not all coated fuel particles in a batch fail after the same irradiation history is due to manufacturing variations in values of individual particle parameters. Two methods of calculating the failure fraction as a function of burnup in terms of these statistical variations are discussed: (a) a random sampling of particles combined with a simple stress model, and (b) the convolution of the individual variations combined with an advanced stress model. These methods were applied to particles manufactured by two laboratories in support of the U.K. low-enriched fuel cycle high-temperature reactor design. Experimental values of variations in the following parameters were included: kernel diameter and porosity, thickness of buffer, seal, silicon carbide and inner and outer pyrocarbon layers (all assumed to be normally distributed), and the silicon carbide fracture stress (assumed to obey a Weibull distribution). It was concluded that the convolution approach was the more satisfactory method. The results enable one to identify which of the various parameters considered are the most worthwhile for manufacturers to put development effort into so as to reduce their variability. For the particles considered here, these are primarily silicon carbide fracture stress, followed by kernel porosity.