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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.
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
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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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Latest News
Biden executive order to facilitate AI data center power
As demand for artificial intelligence and data centers grows, President Biden issued an executive order yesterday aimed to ensure clean-energy power supply for the technology.
Ronald C. Brockhoff, J. Kenneth Shultis
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE07-A2641
Articles are hosted by Taylor and Francis Online.
Empirical parameters for a new fast-neutron differential dose albedo formula are presented for water, concrete, iron, and lead and for ten energy bands between 0.1 and 10.0 MeV. Data are also presented for 252Cf spontaneous fission neutrons, 14-MeV neutrons, and thermal neutrons. The 24-parameter approximation, based on modern dose units, agrees with MCNP-calculated values within 10%. Revised data are also presented for a five-parameter secondary-photon albedo formula, proposed earlier by Maerker and Muckenthaler, that is within 20% of MCNP values for the four materials. Finally, these revised albedo formulas are applied to the problem of thermal neutrons transmitted through a three-legged duct and compared to previous experimental results.