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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
G. G. Simons, A. P. Olson
Nuclear Science and Engineering | Volume 53 | Number 2 | February 1974 | Pages 176-196
Technical Paper | doi.org/10.13182/NSE74-A23343
Articles are hosted by Taylor and Francis Online.
Absolute gamma-ray heating was investigated in Assembly 2 of the Zero Power Plutonium Reactor (during operation in support of the Demonstration Reactor Benchmark critical program). Three loading configurations were studied: loading 90, normal plate core; loading 156, core with central control rod of boron carbide plus sodium; and loading 157, core with central control rod of tantalum plus sodium. All measurements were made with 7LiF thermoluminescent dosimeters encapsulated in a variety of electron-equilibrium sleeves, and the results are compared with calculated doses. This paper gives details of both the experimental procedures and the calculational techniques used to obtain gamma-radiation dose distributions.