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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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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
J. Sanz, O. Cabellos, P. Yuste, S. Reyes, J.F. Latkowski
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 996-1002
Safety and Environment | doi.org/10.13182/FST01-A11963372
Articles are hosted by Taylor and Francis Online.
Inertial confinement fusion (ICF) devices, both test/experimental facilities and fusion energy (IFE) power plants, will operate in a pulsed mode. However, the pulsing schedule in these devices is very different, and it could range from one shot every several days in an experimental facility to some Hz in IFE reactors. The main objective of the present work is to determine whether or not a continuous-pulsed (CP) approach could be an accurate and practical methodology in modeling the pulsed activation experienced by chamber materials of both types of devices. In testing the applicability of the CP irradiation model, we used materials and neutron environment scenarios of the HYLIFE-II reactor and the NIF experimental facility. It is demonstrated that a CP approach consisting of a continuous irradiation period followed by a series of only a few pulses prior to shutdown, can efficiently model the real pulsed operating regimes of the chamber materials, in terms of both accuracy and CPU time consumption. Pros and cons of the model when compared with an equivalent steady-state (ESS) method are discussed, and comparison with the exact pulsed (EP) modeling is also performed.