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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
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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.
Vincent P. Manno
Nuclear Technology | Volume 48 | Number 3 | May 1980 | Pages 281-288
Technical Paper | Fuel | doi.org/10.13182/NT80-A32474
Articles are hosted by Taylor and Francis Online.
The current regulatory requirement that peak cladding temperatures (PCTs) never exceed 1204°C (2200°F) at any time during a loss-of-coolant accident (LOCA) is frequently the most limiting factor in setting core peaking factor limits. Of the many plant specific characteristics involved in predicting a fuel rod’s thermal response to a LOCA, the containment or “back” pressure plays a significant role, especially in pressure suppression pressurized water reactor (PWR) containments. The back pressure effect is studied by comparing the predicted PCT histories at back pressure levels of 138, 155, 172, and 207 kN/m2 (20, 22.5, 25.0, and 30 psia). A typical four-loop PWR with 15 × 15 fuel assemblies is analyzed. The analysis is performed using an in-house LOCA code named HEATUP-R/AEP, which calculates fuel thermal response during core reflood. In addition to temperature, the reflood rates, exit qualities, and cladding oxidation rates are studied. Results show significant increases in PCTs at lower pressure due to enhanced steam binding in the coolant loops.