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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Young Min Kwon, Soon Heung Chang
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 310-328
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3096
Articles are hosted by Taylor and Francis Online.
A model to predict critical heat flux (CHF) for high-heat-flux subcooled flow boiling in uniformly heated tubes is proposed. The present CHF model is based on the mechanism of wall-attached bubble coalescence. To take into account the enhanced condensation due to high subcooling and high mass velocity in small-diameter tubes, a mechanistic approach is adopted to evaluate the nonequilibrium flow quality and void fraction in the subcooled water flow boiling. Comparison of the model predictions against ~3100 subcooled water CHF data shows relatively good agreement over a wide range of parameters that covers the operating conditions of fusion reactor components. The operating ranges of the present database cover 0.33 D 37.5 mm, 0.002 L 4 m, 0.1 P 20 MPa, 0.37 G 134 Mg/m2s, 49 hsub,in 1659 kJ/kg, -1.25 xem < 0, and 1.05 qCHF 276 MW/m2.
