ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
Kostadin N. Ivanov, Tara M. Beam, Anthony J. Baratta, Ardesar Irani, Nicholas G. Trikouros
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 169-186
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3167
Articles are hosted by Taylor and Francis Online.
A comparison of a point-kinetics calculation and a full three-dimensional thermal-hydraulic/kinetics calculation using TRAC-PF1/NEM is presented. The coupled TRAC-PF1/NEM methodology uses version 5.4 of the TRAC-PF1/MOD2 code, developed by the Los Alamos National Laboratory, and a special kinetics module, developed at The Pennsylvania State University and based on the nodal expansion method. Cross sections are obtained from two-dimensional tables generated using CASMO-3.The results of the analysis show that the point-kinetics calculation is conservative and predicts a return to power. The three-dimensional analysis shows no return to power despite an extended overfeeding of the affected generator with feedwater. The difference is believed to be caused by the inability of the standard point-kinetics method to properly account for the moderator density feedback, local effects, and flux redistribution, which occur during the transient.
