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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
J. W. Meadows, J. F. Whalen
Nuclear Science and Engineering | Volume 9 | Number 2 | February 1961 | Pages 132-136
doi.org/10.13182/NSE61-A15597
Articles are hosted by Taylor and Francis Online.
The thermal neutron absorption cross sections of twenty-one naturally occurring elements and B10 have been determined by comparing the time dependence of the neutron flux in water with the time dependence of the neutron flux in a water solution of the sample with the same geometric buckling. After making some small corrections arising largely from the change in the number of hydrogen atoms per cm3 in the solution, the decay constant of the ratio curve gives the macroscopic absorption cross section averaged over the neutron flux spectrum. For a 1/υ cross section the 2200 m/sec cross section can be directly computed. For non-1/υ cross sections the effective 2200 m/sec cross section is obtained.