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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
NRC looks to leverage previous approvals for large LWRs
During this time of resurging interest in nuclear power, many conversations have centered on one fundamental problem: Electricity is needed now, but nuclear projects (in recent decades) have taken many years to get permitted and built.
In the past few years, a bevy of new strategies have been pursued to fix this problem. Workforce programs that seek to laterally transition skilled people from other industries, plans to reuse the transmission infrastructure at shuttered coal sites, efforts to restart plants like Palisades or Duane Arnold, new reactor designs that build on the legacy of research done in the early days of atomic power—all of these plans share a common throughline: leveraging work already done instead of starting over from square one to get new plants designed and built.
N. J. Olson, C. M. Walter, W. N. Beck
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 134-151
Technical Paper | Fuels for Pulsed Reactor / Fule | doi.org/10.13182/NT76-A31547
Articles are hosted by Taylor and Francis Online.
A reasonably large number (39) of Mark-IA driver fuel cladding failures have been obtained from run-to-failure experiments in the Experimental Breeder Reactor II over the past few years. These experiments were designed to yield failure information for various design variables and to qualify the fuel element design to a burnup limit such that the risk of an end-of-design-life failure was exceedingly small for normal operating conditions. None of the design variables or operating conditions tested had a significant effect on the failure statistics. The failure mode fit the Weibull statistical failure model and is characterized by a burnup threshold of 3.0 at.% maximum burnup (BUmax), which must be surpassed prior to failure. The cumulative failure probability [F(BUmax)] for peak linear pin powers between 6.4 and 8.0 kW/ft and maximum cladding temperatures from 890 to 1050°F can be expressed as Once 3.0 at.% BUmax is achieved, it was also found experimentally that the failure rate could be decreased over a small burnup interval by lowering the power ratings. The Type 304L stainless-steel cladding in-reactor fracture mode for the Mark-IA driver fuel elements is characterized by inter granular crack propagation that originates at the outside surface of the cladding. This mode of failure appears to be assisted by stress corrosion and potentially deleterious grain boundary precipitation. Although the fracture mode is brittle in nature, uniform mechanical hoop strains >1% are achieved prior to failure.