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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.
Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 205-229
Technical Paper | Fission Reactors | doi.org/10.13182/NT03-A3384
Articles are hosted by Taylor and Francis Online.
The three-dimensional plant simulator TRAC/BF1-ENTRÉE was validated based on a one-pump trip test. Trends in major plant process parameters and three-dimensional power distributions were studied with regard to in-core flow reduction, insertion of control blades, and neutron spectrum mismatch. An improved moderator direct heating model was proposed by separately modeling the neutron slowing down and the gamma-ray absorption mechanism. The delayed heat conduction caused by the gamma heating in metallic regions was implemented. Sensitivities of water level and three-dimensional power were studied by varying the core power history, the dryer loss coefficient, and the neutron kinetics solution approach.