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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
Aaron M. Phillippe, James E. Banfield, Kevin T. Clarno, Larry J. Ott, Bobby Philip, Mark A. Berrill, Rahul S. Sampath, Srikanth Allu, Steven P. Hamilton
Nuclear Science and Engineering | Volume 177 | Number 3 | July 2014 | Pages 275-290
Technical Paper | doi.org/10.13182/NSE13-18
Articles are hosted by Taylor and Francis Online.
The Integrated Fuel Assessment IFA-432 experiments from the International Fuel Performance Experiments database were designed to study the effects of gap size, fuel density, and fuel densification on fuel centerline temperature in light water reactor fuel. An evaluation of nuclear fuel pin heat transfer in the FRAPCON-3.4 and Exnihilo codes for uranium dioxide (UO2) fuel systems was performed, with a focus on the densification stage (2.2 GWd/tonne UO2). In addition, sensitivity studies were performed to evaluate the effect of the radial power shape and approximations to the geometry to account for the thermocouple hole. The analysis demonstrated excellent agreement for rods 1, 2, 3, and 5 (varying gap thicknesses and density with traditional fuel), demonstrating the accuracy of the codes and their underlying material models for traditional fuel. For rod 6, which contained unstable fuel that densified an order of magnitude more than traditional, stable fuel, the magnitude of densification was overpredicted, and the temperatures were outside the experimental uncertainty. The radial power shape within the fuel was shown to have a significant impact on the predicted centerline temperatures, whereas the effect of modeling the fuel at the thermocouple location as either annular or solid was relatively negligible. This has provided an initial benchmarking of the pin heat transfer capability of Exnihilo for UO2 fuel with respect to a well-validated nuclear fuel performance code.