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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
S. G. Carpenter, J. M. Gasidlo, J. M. Stevenson
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 236-239
Technical Note | doi.org/10.13182/NSE72-2
Articles are hosted by Taylor and Francis Online.
The effective delayed-neutron fractions of 235U and 239Pu have been determined for two fast critical assemblies from measurements of the absolute fission rate and the apparent reactivity worths of a calibrated 252Cf neutron source. The experimental values of βeff for the two fissile isotopes, 0.0078 to 0.00233, respectively, are in reasonable agreement with calculations. The results do not explain the 30% discrepancy in measured and calculated reactivity values in fast critical experiments.
