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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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Latest News
West Valley completes teardown of Mail Plant Process Building
The Department of Energy’s Office of Environmental Management and its cleanup contractor CH2M Hill BWXT West Valley (CHBWV) completed the on-time removal of the Main Plant Process Building at the West Valley Demonstration Project (WVDP) in New York. Located 35 miles south of Buffalo, the 150-acre WVDP site is home to the only commercial spent nuclear fuel reprocessing facility to operate in the United States.
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 80-114
Computer Code Abstract | doi.org/10.1080/00295639.2018.1471296
Articles are hosted by Taylor and Francis Online.
SENSMG is a tool for calculating the first-order sensitivities of reaction-rate ratios, keff, and α in critical problems and reaction-rate ratios, reaction rates, and leakage in fixed-source problems to multigroup cross sections, isotope densities, material mass densities, and interface locations using the PARTISN multigroup discrete-ordinates code by implementing Generalized Perturbation Theory. SENSMG can be used for one-dimensional spherical and slab (r) and two-dimensional cylindrical (r-z) geometries. For fixed-source (leakage) problems, SENSMG relies on the MISC and/or SOURCES4C codes to compute neutron source rate densities from spontaneous fission and (α,n) sources. SENSMG is a combination of Python and Fortran and was developed under Linux. This computer code abstract describes all user inputs, the input file, and output files. This computer code abstract describes how SENSMG can be modified to support different computer platforms, PARTISN versions, or cross-section availability. Several verification problems are presented in which SENSMG results are compared with MCNP6, SCALE6.2, and direct perturbations (central differences). SENSMG is available at https://github.com/jafavorite/SENSMG. SENSMG can be modified to accommodate other deterministic transport codes that have an adjoint capability.