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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
H. M. Eiland, L. J. Esch, F. Feiner, J. L. Mewherter
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 180-189
Technical Paper | doi.org/10.13182/NSE71-A19666
Articles are hosted by Taylor and Francis Online.
The resonance integrals for capture and fission and their ratios, a, have been measured for 233U, 235U, 239Pu, and 241Pu. Small samples of high isotopic enrichment were irradiated in a water channel of a swimming pool reactor. The number of captures was determined by mass spectrometry and the number of fissions was determined by 137Cs analysis. A combination of cadmium and rhodium neutron filters was used to provide effective cutoff energies in the 2- to 4-eV range. The measured values of a above 3.0 eV are 0.148 ± 0.006, 0.615 ± 0.019, 0.723 ± 0.044, and 0.285 ± 0.015 for 233U, 235U, 239Pu, and 241Pu, respectively. The corresponding values calculated from ENDF/B cross sections are 0.162, 0.608, 0.650, and 0.212.
