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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
H. H. Hummel, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 35-46
Technical Paper | doi.org/10.13182/NSE74-A23391
Articles are hosted by Taylor and Francis Online.
A study of the sensitivity of the integral properties of the plutonium-fueled fast-reactor critical assembly ZPR-6, Assembly 7 to uncertainties in the nuclear data has been performed with the aid of the VARI-1D variational sensitivity code; ENDF/B Version III was taken as a reference nuclear data base. The effect of 10% cross-section changes, which were correlated over the entire energy range, was analyzed, and allowed data uncertainties compatible with given uncertainties in integral parameters were established. Estimated uncertainties in important cross sections were considered, and the effect of different assumptions of the correlation in energy of the data uncertainties was examined. The effect of data changes among ENDF/B Versions I, II, and III was also analyzed. The most important data uncertainties are in the fission cross section of 239Pu and in the capture cross section of 238U, while the most important uncertainties in integral properties are in sodium void effect, breeding ratio, and keff. (The Doppler coefficient was not studied in the present work.)
