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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.
Dong H. Nguyen, Marshall T. Slayton, John A. Frew
Nuclear Science and Engineering | Volume 46 | Number 3 | December 1971 | Pages 416-421
Technical Note | doi.org/10.13182/NSE71-A22379
Articles are hosted by Taylor and Francis Online.
Transport parameters (migration area, age to indium resonance) of fast neutrons from a plutonium -beryllium source have been measured in aqueous absorbing solutions at several temperatures (35, 40, 55, and 75°C), using boric acid as the 1/ absorber. For the measurements at 35 and 40°C, the saturation concentrations of boric acid were attained at 70 and 80 g/liter, respectively. For a 1/ absorber, a temperature-dependent power series representation of k2 in terms of absorption cross section ∑ao was proposed, based on the concept of neutron temperature. The temperature range wherein such an expansion remains valid was experimentally determined. It was found that strong concentrations of a 1/ absorber caused much difficulty in experimentally resolving the thermal neutron spatial distributions, an observation which might have a direct relation to the (∑t)min limit of Corngold.
