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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
J. H. Brindley
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 313-328
Technical Paper | doi.org/10.13182/NSE65-A21067
Articles are hosted by Taylor and Francis Online.
Flat-plate fuel-element surface temperatures in the Organic Moderated Reactor Experiment were monitored by 0.005-in. (0.013-cm)-diam chromel-alumel thermocouple wires, spot-welded to the stainless-steel fuel-plate surface. The thermocouple assembly, being exposed to the coolant stream, is subject to thermal-loading errors; as a result, thermocouple-calibration tests were performed in a forced-convection heat-transfer loop with Santowax O-M flowing over an electrically heated test plate containing typical thermocouple specimens. The tests were conducted under the following simulated reactor conditions: coolant temperatures from 300 to 600°F (149 to 316°C), coolant velocities from 10 to 20 ft/sec (3.1 to 6.1 m/sec), and heat fluxes ranging from 0.50 × 105 to 1.6 × 105 Btu/(h ft2) (15.77 to 50.46 W/cm2). Test results demonstrate that at reactor operating conditions, 600 °F organic coolant flowing at 17.5 ft/sec (5.34 m/sec), the observed fuel-plate surface temperature is 700 °F (371 °C), while, in reality, the actual surface temperature is 750 °F (399 °C). The thermocouple thermal-loading errors were found to be a function of the coolant Reynolds and Prandtl numbers. Heat flux had no effect on the calibration. Excellent agreement was obtained between the experimental and predicted (Dittus-Boelter) heat-transfer coefficients for the organic coolant. Thermocouple-calibration factors for correction of observed surface temperatures over a wide range of operating conditions, are presented as a function of the organic-coolant heat-transfer coefficient on the fuel-plate surface. An electrical-analogue model of a thermocouple assembly on the surface of an OMRE fuel element was constructed to: a) verify experimental results; b) study the effect of a fouling film on surface-temperature measurements; and c) provide an inexpensive means of calibrating surface-attached thermocouples on fuel plates for future use. Prediction of thermal-loading errors associated with this type of surface-temperature measurement by the use of existing mathematical results is discussed. Good agreement was obtained between the electrical-analogue results, the analytical predictions, and the experimental data. Film formation on the fuel plate and the thermocouple wire was observed to reduce the thermocouple-calibration factor by as much as 45%.