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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.
Pedro Mata, Rafael de la Fuente, Pablo G. Sedano, Juan Serra
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 275-288
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2839
Articles are hosted by Taylor and Francis Online.
The development of a reload transient analysis methodology for Cofrentes nuclear power plant is presented based on the RETRAN-03 code. The starting point of this methodology was the Cofrentes best-estimate RETRAN model, which had been benchmarked against a number of startup and operational transients. In addition, the best-estimate model had been used to support plant operation and to analyze actual operational and abnormal transients.A number of sensitivity studies have been carried out with the best-estimate model to analyze the effect of the uncertainty associated with the key parameters on the critical power ratio in the most limiting Cofrentes reload transients. The individual uncertainties of key parameters have been combined to obtain the change in critical power ratio (CPR) with a 95% probability level (CPR95).Finally, the Cofrentes licensing model has been defined using conservative values for some significant parameters with the criterion that the calculated CPR cover CPR95. The results obtained with the licensing model have been checked against vendor calculations for the licensing reload transients.This methodology has been submitted to the Spanish Regulatory Commission, and it is expected to be used for the next Cofrentes reload licensing analysis.