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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
Scott D. Ramsey, Roy A. Axford, Gregory J. Hutchens
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 73-81
Technical Note | doi.org/10.13182/NSE09-63TN
Articles are hosted by Taylor and Francis Online.
Stochastic point kinetics neglecting delayed neutrons has been subject to rigorous analysis in the years since its introduction. Many approximate solutions appearing within this context are based upon the “quadratic approximation,” where fission multiplicity is truncated at two. In this technical note we review the quadratic approximation within the context of a stochastic, space-independent, one-energy-group model neglecting delayed neutrons and its generalization to higher-order approximations in transient and stationary systems. This generalization results in the probability of a zero neutron population for a source-free system being governed by transcendental and polynomial algebraic equations in the transient and infinite time limit cases, respectively. For 239Pu, we solve the transcendental equation over a wider range of prompt multiplication factors and times than has been previously accomplished. We also reproduce and generalize associated solutions of the polynomial algebraic equation. In both cases, solutions are computed for successive generalizations of the quadratic approximation to higher-order maximum fission multiplicity.