ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
C. A. Brandon, G. J. Kidd, Jr.
Nuclear Science and Engineering | Volume 32 | Number 1 | April 1968 | Pages 8-15
Technical Paper | doi.org/10.13182/NSE68-A18818
Articles are hosted by Taylor and Francis Online.
During a series of in-pile experiments designed to study irradiation effects on high-performance oxide fuel elements for advanced gas-cooled reactors, heat-transfer data were obtained from four specially instrumented fuel rods. An annular geometry was utilized with rods of 1.9- and 2.18-cm diam being contained in channels of 2.44- and 2.67-cm diam, respectively. The effects of wire-wrapped and machined square-thread surface roughness were measured and compared with the results obtained from a smooth rod. The fuel rods contained UO2 pellets of varying enrichment and were clad with type-304 stainless-steel tubing. The test parameters for the data reported are: 1) coolant flow rate from 45 to 150 kg/h of helium at 20 atm which corresponds to Reynolds numbers from 15 000 to 45 000; 2) cladding temperatures to 840°C; and 3) heat fluxes from 30 to 100 W/cm2. The smooth-rod data can be correlated with a standard deviation of ±10% by the expression Roughening the rods increased the heat transfer by approximately a factor of 2 with no significant difference between the wire-wrapped and machined roughnesses. The results are generally found to be in good agreement with the results of previous heat-transfer studies. Some consequences of using heat-transfer promoters in nuclear reactor fuel elements are discussed.