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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.
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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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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.
U. Salmi, J. J. Wagschal, A. Yaari, Y. Yeivin
Nuclear Science and Engineering | Volume 84 | Number 3 | July 1983 | Pages 298-300
Technical Note | doi.org/10.13182/NSE83-A17799
Articles are hosted by Taylor and Francis Online.
Several widely used neutron transport codes approximate the fission-source matrix by accepting only a single fission-neutron spectrum, regardless of how this spectrum is selected. This approximation introduces a needless calculational error. To overcome this flaw the difference between the correct and the approximate fission source matrices should be added to the scattering matrix. This significantly reduces the calculational errors in integral parameters calculated in the k formulation of the stationary transport equation and eliminates these errors altogether when the integral parameters are calculated in the other formulations of the equation. A numerical example is provided to demonstrate these points. The reactivity k, the average neutron energy , and the ratio are calculated for a JEZEBEL-like assembly using the standard and the proposed procedures.
