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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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Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
J. Richard Smith, John J. King, J. Wiley Davidson, Morris E. Battat
Fusion Science and Technology | Volume 23 | Number 1 | January 1993 | Pages 51-67
Technical Paper | Blanket Engineering | doi.org/10.13182/FST93-A30119
Articles are hosted by Taylor and Francis Online.
An experiment to measure the multiplication of 14-MeV neutrons in bulk beryllium has been completed. The experiment consisted of determining the ratio of 56Mn activities induced in a large manganese bath by a central 14-MeV neutron source, with and without a beryllium sample surrounding the source. The superior isotropy and flat energy response of the manganese bath gives this detector an advantage over the inhomogeneous and anisotropic detector arrays used in previous experiments for measurements of this type. Values of the multiplication have been obtained for beryllium samples of four thicknesses. The measurements are affected by several systematic effects characteristic of the manganese bath. The values of these systematic corrections are established by a combination of calculation and experimental parameterization. Detailed calculations of the multiplication and all the systematic effects are made by using a highly detailed three-dimensional Monte Carlo geometry model with the MCNP Monte Carlo program. The Young-Stewart and the ENDF/BVI evaluations for beryllium are used in the analysis. Both data sets produce multiplication values that are in excellent agreement with the manganese bath measurements for both raw and corrected values of the multiplication. It is concluded that there is no real discrepancy between experimental and calculated values for the multiplication of neutrons in bulk beryllium.