ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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June 2024
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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
D. Rochman, M. Herman, P. Oblozinský, M. Sin
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 280-293
Technical Paper | doi.org/10.13182/NSE06-A2633
Articles are hosted by Taylor and Francis Online.
Neutron-induced fission cross sections for eight americium isotopes (A = 239 to 244) are predicted with the nuclear reaction model code EMPIRE-2.19. The code incorporates advanced fission modeling, presented by describing the implementation of barrier penetration, transmission mechanism, and decay probabilities. The fission cross-section calculations for americium isotopes are compared to experimental data and evaluations from the ENDF/B-VI.8, JEFF-3.1, JENDL-3.3, or preliminary ENDF/B-VII libraries when available. An analysis of the first and second fission barrier heights validates the existing systematic trend for odd and even neutron numbers.
