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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
Akira Sakurai, Masahiro Shiotsu, Koichi Hata
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 321-330
Technical Paper | doi.org/10.13182/NSE84-A18586
Articles are hosted by Taylor and Francis Online.
Film-boiling heat transfer on a horizontal test heater in a pool of saturated and subcooled water was investigated at pressures ranging from 20 kPa to 2 MPa. Platinum rods of 0.7, 1.2, 2, 3, and 5 mm in diameter were used as the test heater. A semiempirical equation and a modified Bromley equation were given, both of which could express the saturated film-boiling heat transfer coefficients within ±5% error. The heat transfer coefficients for a certain range of heater diameters under saturated and subcooled conditions were expressed within ±10% error by the two-phase boundary-layer film-boiling model with the boundary condition of equal liquid and vapor interfacial velocities. Pressure dependence of the minimum film-boiling temperature for pressure <1.1 MPa was clearly different from that for pressure >1.1 MPa. Minimum temperature in the lower pressure region seems to be determined by the hydrodynamic Taylor instability and that in the higher pressure region by the heterogeneous spontaneous nucleation limit. However, minimum temperature and heat flux of saturated film boiling in the former region did not agree with those of conventional equations based on the Taylor instability. Empirical equations of interfacial wave length, departing bubble diameter, and frequency near the minimum film-boiling temperature for the lower pressure region were given. Minimum temperature and heat flux equations were presented based on these empirical equations.