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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
José Canosa
Nuclear Science and Engineering | Volume 19 | Number 3 | July 1964 | Pages 329-342
Technical Paper | doi.org/10.13182/NSE19-03-329
Articles are hosted by Taylor and Francis Online.
The problem of adiabatic excursions in a reactor is studied in general. We let the prompt temperature reactivity feedback be an unspecified function of temperature, ρ = ρ0 = ρ0 + f(T), where ρ is total reactivity, ρ0 initial step reactivity and f(T) the feedback function. The similarity of the behavior of the reactor for different f(T) is established by means of a topological (qualitative) analysis. A quantitative asymptotic solution of the non-linear system of DE describing the reactor is presented. In delayed critical excursions, the delayed neutrons play a determining role. In the first part of a prompt excursion, the delayed-neutron source is nil; however this is not so in the second part, where it contributes appreciably to the excursion. These conclusions are shown to be valid in general, and allow us to write down almost directly the (approximate) quantitative solution of the non-linear system for any f(T). These results are correlated with the experimental data for the adiabatic excursions of a UO2 core in SPERT I; in this case the (prompt) dependence of the reactivity on energy is of the form ρ = ρ0 - 4.588 × 10-4E0.74.