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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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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February 2025
Latest News
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
S. R. Bierman, B. M. Durst, E. D. Clayton, R. I. Scherpelz, Howard T. Kerr
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 141-151
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32247
Articles are hosted by Taylor and Francis Online.
A series of criticality experiments with fast test reactor (FTR) fuel pins in water has been performed in support of the Advanced Fuel Recycle Program (AFRP). The objective of these experiments was to provide clean, easily defined criticality data on AFRP-type fuel pins in water for use in verifying calculational techniques and nuclear data used in calculations. Measurement data were obtained on water-flooded square lattices of FTR fuel pins. The number of fuel pins required for criticality was determined at lattice pitches of 7.7, 9.5, 9.7, 12.6, 15.3, and 19.1 mm to be 1268, 605, 580, 219, 205, and 162, respectively. These center-to-center fuel pin spacings correspond to water-to-fuel volume ratios of 1.61, 3.33, 3.49, 6.81, 10.88, and 17.53, respectively, and cover the neutron moderation range from near optimum to the highly undermoderated. KENO-IV calculations with ENDF data from the AMPX system overestimated the experimental results by 1 to 2% in keff. KENO-IV calculations with FLANGE-ETOG-THERMOS-EGGNIT-processed ENDF data resulted in calculated values 1 to 6% high in keff.
