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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.
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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.
M. Antonopoulos-Domis, C. Housiadas
Nuclear Science and Engineering | Volume 132 | Number 3 | July 1999 | Pages 337-345
Technical Paper | doi.org/10.13182/NSE99-A2068
Articles are hosted by Taylor and Francis Online.
Estimation of the moderator temperature coefficient (MTC) of reactivity of pressurized water reactors by noise analysis is investigated, both theoretically and through numerical simulations. It is found that using local neutron signals, all estimators of MTC will underestimate the actual MTC value, as indeed is observed in all measurements reported in the literature. However, the relative deviation from the actual MTC value remains practically constant over a wide range of MTC values. This suggests that it is possible to calibrate the estimate at the beginning of the fuel cycle and then use this calibration until the end of the fuel cycle. A new estimator is proposed based on integral (point model) concepts. This estimator is found capable of providing the actual value of MTC, provided that coolant velocity fluctuations are at least as strong as coolant inlet temperature fluctuations in inducing neutron and coolant temperature fluctuations.