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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.
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2021 Student Conference
April 8–10, 2021
Virtual Meeting
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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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NC State celebrates 70 years of nuclear engineering education
An early picture of the research reactor building on the North Carolina State University campus. The Department of Nuclear Engineering is celebrating the 70th anniversary of its nuclear engineering curriculum in 2020–2021. Photo: North Carolina State University
The Department of Nuclear Engineering at North Carolina State University has spent the 2020–2021 academic year celebrating the 70th anniversary of its becoming the first U.S. university to establish a nuclear engineering curriculum. It started in 1950, when Clifford Beck, then of Oak Ridge, Tenn., obtained support from NC State’s dean of engineering, Harold Lampe, to build the nation’s first university nuclear reactor and, in conjunction, establish an educational curriculum dedicated to nuclear engineering.
The department, host to the 2021 ANS Virtual Student Conference, scheduled for April 8–10, now features 23 tenure/tenure-track faculty and three research faculty members. “What a journey for the first nuclear engineering curriculum in the nation,” said Kostadin Ivanov, professor and department head.
Scott D. Ramsey, Roy A. Axford
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 48-57
Technical Paper | dx.doi.org/10.13182/NSE09-64
Articles are hosted by Taylor and Francis Online.
We implement direct and approximate local sensitivity analysis techniques within the context of stochastic point kinetics neglecting delayed neutrons and external neutron sources. After reviewing the derivation of certain probabilities that the neutron population in a nuclear assembly is exactly zero [probabilities of extinction (POEs)], we consider their dependence on physical data. We subsequently focus on fission number distribution dependence and draw comparisons between two different data sets. As various POEs are dependent upon these data through the solution of a nonlinear ordinary differential equation, local sensitivity analysis provides a useful means through which to assess the effects of data reevaluation. We first conduct this analysis generally (though approximately) using Gâteaux-derivative methodology. Following the generalized developments, exact and approximate results for 235U are presented with a discussion concerning important consequences related to criticality safety.