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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
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Strong performances across the board
Craig Piercycpiercy@ans.org
Another year, another stellar performance by America’s nuclear plants. We’ve come to expect high capacity factors, and it’s a credit to the men and women of the profession. They’ve made routine something that was unimaginable not so long ago.
The decadal challenge for the nuclear enterprise now is to maintain this high level of operational excellence for the current fleet, while at the same time ushering in a new generation of technologies at scale. It will be a big job—but one that seems more and more likely with each passing day.
Zhiwen Xu, Michael J. Driscoll, Mujid S. Kazimi
Nuclear Science and Engineering | Volume 141 | Number 3 | July 2002 | Pages 175-189
Technical Paper | doi.org/10.13182/NSE02-A2277
Articles are hosted by Taylor and Francis Online.
To provide guidance for future light water reactor core design and fuel management strategies, the effects of the moderator-to-fuel ratio on burnup, core endurance, and waste disposal characteristics have been investigated. The analysis is based on a unit cell model of the standard four-loop Westinghouse pressurized water reactor (PWR) with varied water density, rod diameter, and lattice pitch. Two state-of-the-art computer codes, CASMO-4 and MOCUP (MCNP+ORIGEN), have been used. Considering the entire range of moderation (from fast spectra to overthermalized spectra), the results show that higher reactivity-limited burnup is achievable by either a wetter lattice or a much drier lattice than normal. In particular, epithermal lattices are distinctly inferior performers. Current PWR lattices are about the optimum in terms of highest fuel endurance. However, wetter lattices produce less plutonium with a degraded plutonium isotopic mix with respect to weapons usability. Neptunium-237 content is only mildly affected by the hydrogen-to-heavy-metal ratio. High burnup is significantly beneficial to reducing plutonium production per unit energy and to making its isotopic mix less attractive as a weapon material. In particular, the 238Pu to 239Pu ratio increases approximately as the 2.5 power of burnup for a fixed initial enrichment. Based on this neutronics study, wetter lattices are recommended for future high-burnup applications.