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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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.
R. W. Stoughton, J. Halperin, C. E. Bemis, H. W. Schmitt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 169-171
Technical Note | doi.org/10.13182/NSE73-A23241
Articles are hosted by Taylor and Francis Online.
The neutron multiplicities P(n) in the spontaneous fission of 246Cm, 248Cm, and 252Cf have been measured in a 3He neutron counter assembly. The efficiency ∈ for detection of a single neutron was measured to be 0.360, based on (average number of neutrons per fission) = 3.73 for 252Cf spontaneous fission. Using this value of ∈ and assuming a Gaussian distribution p(v) for the emitted neutrons, we fitted our observed P(n), corrected for small background and pile-up effects, to the model by the method of least squares in which the Gaussian width σv and were the parameters of fit. Values of p(v) were then calculated from the resulting Gaussian function. In the case of 252Cf, our values of p(v) agree well with literature values; the p(v) values for the curium isotopes have not been measured previously as far as we know. The values of for both 246 Cm and 248Cm fall on a straight line through existing experimental values for the nuclides 242Cm, 244Cm, and 250Cm in a plot of versus mass number; our values were 2.86 ± 0.06 and 3.14 ± 0.06 for 246Cm and 248Cm, respectively.