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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
M. Ishii, H. K. Fauske
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 131-146
Technical Paper | doi.org/10.13182/NSE83-A17719
Articles are hosted by Taylor and Francis Online.
For certain postulated severe accident conditions such as a loss of piping integrity and a loss of heat sink in connection with liquid-metal fast breeder reactor safety analysis, the process of decay heat removal can lead to coolant boiling. For such low-heat-flux/low-flow conditions, a dryout or critical heat flux criterion is required in order to assess the potential for fuel pin failure and melting. Computer codes and full-scale experimental data are not available to completely address this problem at this time. Based on the interpretation of available experimental data and new analyses, it is concluded that a typical subassembly can be safely cooled (avoid dryout) under natural convection conditions for heat fluxes below ∼8 to 10% of the average nominal power; i.e., decay heat power levels can be safely accommodated in the natural convective regime. Furthermore, since this coolability limit is predicted to be rather insensitive to the subcooling value, it follows that the safety case relative to decay heat removal for an intact core geometry also becomes essentially independent of detailed accident conditions such as the potential for temporary stagnated flow or inlet flow reversal conditions.