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2025 ANS Winter Conference & Expo
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).
Jan-Li Wang, Jay F. Kunze
Nuclear Technology | Volume 85 | Number 3 | June 1989 | Pages 285-293
Technical Paper | Nuclear Safety | doi.org/10.13182/NT89-A34250
Articles are hosted by Taylor and Francis Online.
The RELAP5 thermal-hydraulic transient code has been applied to a reactor safety analysis of a loss-of-coolant accident (LOCA) to a reactor with thin fuel plates operating at highly subcooled conditions, ∼75°C below boiling temperatures at operating pressure, 25°C below boiling conditions at atmosphere pressure that occurs immediately following the LOCA. Depressurization is not the critical issue in this case, but plate boiling and reflooding and mixing of vapor and fluid streams are the critical aspects of the calculation. The analysis of the results shows the sensitivity of the calculation to the time periods of the steam “chugging” effects in the water channels between fuel plates. This MOD2 version is the first version with which we found consistency and realism in the results calculated for these very difficult transient conditions.