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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
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.
C. V. Parks, P. J. Maudlin
Nuclear Technology | Volume 54 | Number 1 | July 1981 | Pages 38-53
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32752
Articles are hosted by Taylor and Francis Online.
A recently proposed sensitivity technique called differential sensitivity theory is applied to the neu-tronic/thermal-hydraulic fast reactor safety code MELT-IIIB. This application centers on the develop ment and solution of the appropriate adjoint and sensitivity equations, resulting in an adjoint version of the MELT code called MELTADJ. Proper inte gration of the forward MELT solution with the corresponding adjoint MELTADJ solution formally yields sensitivity information for all input parameters. Two transients in the Fast Flux Test Facility were investigated by performing input parameter sensi tivity analyses. Sensitivities obtained via MELTADJ are compared with those from MELT recalculations using perturbed input. These investigations indicate sufficiently good agreement between differential sensitivity theory and recalculation to validate the development of MELTADJ.