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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
W. Breitung
Nuclear Science and Engineering | Volume 108 | Number 1 | May 1991 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE91-A23804
Articles are hosted by Taylor and Francis Online.
Measurements of the total pressure from irradiated (U,Pu)-mixed oxide were analyzed with respect to the fission product release kinetics and availability for pressure generation in Bethe-Tait excursions. Two pressure sources acting on a millisecond time scale were identified: release of grain boundary fission products (gases and volatiles such as cesium) triggered by grain boundary separation and release of formerly intragranular fission products due to fuel boiling. The former process can provide pressures on a megapascal scale early, and the latter process, late in the accident progression. No fission product release was observed from nonboiling liquid fuel. Based on the experimental data, a model was formulated for the total pressure over irradiated (U,Pu)-oxide. Fuel vapor and gases interact by a suppression mechanism: pIF = max(pAG + pFP, psat). The total pressure over irradiated fuel pIF is equal to the pressure sum from ambient gas pAG and released fission products in the gaseous state pFP when this sum is greater than the saturation vapor pressure of fresh (U,Pu)-oxide psat. In this regime, fuel boiling is suppressed. At sufficiently high temperatures when psat > pAG + pFP, the oxide begins to boil and the total pressure pIF reaches the fresh fuel saturation vapor pressure psat. The switch-over in the controlling mechanism occurred at ∼5200 K.
