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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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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.
Jun Wang (Univ of Wisconsin, Madison), Anil Gurgen (MIT), Michael L. Corradini (Univ of Wisconsin, Madison), Koroush Shirvan (MIT)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 755-762
In order to compare the thermal hydraulics system response to Accident Tolerant Fuel (ATF) materials, a benchmark was performed for early accident progression behavior given a Station Blackout scenario. Thermal hydraulic parameters such as the pressurizer pressure, reactor pressure vessel (RPV) water level, peak cladding temperature, and hydrogen mass generated were quantified by the TRACE code by a team at MIT and compared to MELCOR by a team at UW Madison. This benchmark comparison with TRACE and MELCOR used the same initial conditions for a simplified generic PWR plant model. This PWR model was based on a 2200MWth conventional light water reactor plant. The benchmark work included the input model development and the simulation comparisons for the thermal hydraulic response, pressurizer relief valve operation, and the clad oxidation. The Zircaloy cladding case and FeCrAl cladding case were compared in the current simulation. The result showed good agreement between TRACE and MELCOR for overall event timing and key parameters. The exothermic energy release from Zircaloy and FeCrAl clad oxidation were calculated and compared. The difference in oxidation energy between the clad materials was quite small when compared to decay heat values.
