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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
L. R. Fawcett, Jr.
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 173-183
Technical Paper | doi.org/10.13182/NSE93-A24006
Articles are hosted by Taylor and Francis Online.
Tritium production in a sphere of 6LiD with an Oralloy core irradiated by a central source of 14-MeV neutrons has been calculated and compared with experimental measurements. The experimental assembly consisted of an Oralloy sphere surrounded by three solid 6LiD concentric shells with ampoules of 6LiH and 7LiH located in several positions throughout the assembly. The Los Alamos Monte Carlo Neutron Photon Transport Code (MCNP) was used to calculate neutron transport throughout the system and tritium production in the ampoules. The MCNP calculations were three-dimensional and employed ENDF/B- V cross sections. The overall experimentally observed-to-calculated ratios of tritium production were 0.996 (±2.5%) in 6LiH ampoules and 0.903 (±5.2%) in 7LiH ampoules. Tritium production in a sphere of 6LiD without an Oralloy core has been reanalyzed using ENDF/B-V cross sections, and the results are reported. The reanalyzed observed-to-calculated values of tritium production were 1.053 (±2.1%) in 6LiH and 0.999 (±2.1%) in 7LiH. The foregoing several uncertainties do not include an estimated <6% systematic error in the observed values.
