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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
K. V. Subbaiah, A. Natarajan, D. V. Gopinath, D. K. Trubey
Nuclear Science and Engineering | Volume 81 | Number 2 | June 1982 | Pages 172-195
Technical Paper | doi.org/10.13182/NSE82-A20084
Articles are hosted by Taylor and Francis Online.
The contribution of bremsstrahlung, annihilation, and fluorescence radiation to the spectra of scattered gamma radiation and to the dose buildup factors has been investigated as a function of source energy, atomic number, and sample thickness over an energy range of 0.1 to 8 MeV. The computations were performed with the one-dimensional transport code ASFIT modified to take into account all the secondary radiations. The required mathematical formulation, along with representative results obtained for uranium, lead, iron, and water, typifying materials of very high, high, medium, and low atomic number, are presented and discussed. A noticeable effect of including bremsstrahlung sources is the general softening of the scattered radiation spectra inside the medium and at the exit. This effect is more pronounced in materials of high atomic number. The bremsstrahlung contribution is seen most prominently in the reflection spectra above 0.511 MeV, where the contribution from other processes is insignificant. The effect of annihilation radiation is significant in the region between 0.511 MeV and the K edge, below which the effects of fluorescence radiation overshadow all others. Peaks and discontinuities characteristic of single scatterings of these radiations are seen in the reflection spectra, gradually disappearing with depth in the medium. The effect of fluorescence on the dose buildup factor is spectacular for source energies close to the K edge and falls off rapidly thereafter. The impact of bremsstrahlung, on the other hand, steadily rises with source energy. The influence of annihilation radiation is comparatively modest and is significant only for systems of intermediate atomic numbers.