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November 9–12, 2025
Washington, DC|Washington Hilton
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OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
G. Melese-d'Hospital
Nuclear Science and Engineering | Volume 35 | Number 2 | February 1969 | Pages 165-175
Technical Paper | doi.org/10.13182/NSE69-A21132
Articles are hosted by Taylor and Francis Online.
If the coolant mass flow were constant across the core, the coolant temperature rise would be proportional to the channel power. But, without orificing, the coolant mass flow in the hot channel is smaller than the average flow while the outlet temperature is hotter than the mixed mean temperature. The approximate radial distributions of coolant mass flow (M/M0) and temperature rise (ΔT/ΔT0) are shown to depend only upon the (arbitrary) radial flux distribution (H/H0) and upon a single lumped core parameter (δ), proportional to the product of the pressure by the pressure drop. For simple radial flux distributions and when δ goes from zero to infinity, (M0/Mav) increases approximately from (Hav/H0) to one, while (ΔT0/ΔTav) decreases approximately from (H0/Hav)2 to (H0/Hav). The relationships between hot channel parameters, maximum clad or fuel temperatures, and thermal power are derived in the Appendix for a “chopped cosine” axial flux distribution.