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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Gang Jiang, Gang Chen, Weikun Ding, Yanghua Yang (State Power Investment Corporation Research Inst)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 388-398
After the Fukushima accident, the lessons involving in nuclear emergency management show that the emergency decision should enhance the capacity of analyzing and predicting severe accident. In order to improve this capability, the severe accident management training simulator (SAMTS) has been developed. This simulator has transplanted the self-developed integral severe accident code cosSA to the simulation platform to build the accident scenario, and coupled with computerized severe accident management guideline (CSAMG). The SAMTS provides several interventions to simulate different mitigation measures in SAMG, which help the operators handle to mitigate consequences and understanding the impact of mitigating actions on accident progression. This simulator could build the accident scene quickly to forecast and analysis to make central role of the information source for decision-making technical support in nuclear emergency management. The main purpose of this paper is to give a brief description of this simulator, including architecture, methodology, physical models of cosSA and a simulation case. Simulation results were compared with MELCOR (mainstream simulator calculation engine service) with the same initial and boundary conditions. Comparison results show that the calculation results of temperature, pressure and water level by SAMTS agree well with MELCOR. The good agreement proves the simulation capability of cosSA, which shows that cosSA could be applied into the severe accident simulator.
