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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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Latest News
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Om Pal Singh, P. Bhaskar Rao
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 411-416
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33693
Articles are hosted by Taylor and Francis Online.
The core disruptive accident (CDA) analysis of liquid-metal fast breeder reactors is often performed using the saturated vapor pressure equation of state for the fuel. However, during the transient heating of the fuel in a voided core in the disassembly phase of CDAs, the fuel vapor pressure buildup may lag behind the temperature rise and thus may lead to the delayed disassembly of the core and the consequent large energy release. The formulations for such transient vapor pressure buildup and the results on the dynamics of fuel vapor pressure during the transient heating and its influence on the thermal energy release in a CDA are presented. The energy release calculations have been performed by incorporating the present formalism in the disassembly analysis code VENUS-II. In view of the uncertainties in some of the physical parameters, a parametric study was conducted to evaluate the effects of such uncertainties in their values on the results. These results are discussed in detail.