| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 5475255 | Annals of Nuclear Energy | 2017 | 14 Pages |
Abstract
This work describes a cross section analysis using a KRITZ experiment modeled with the MCNP code for different ENDLs. The first goal is to validate the processing cross section at work temperature using the KRITZ benchmark for all the evaluated nuclear data libraries available, ENDF-VII.1, JEFF-3.1, JEFF-3.2, TENDL-2014, TENDL-2015, JENDL-4.0, RUSFOND and CENDL-3 at DEN/UFMG. The second goal is to use the same experiment (geometry, parameters, etc) at KRITZ benchmark and use it for thorium application. The new fuel based on thorium were spiked with different fissile nuclides such as 233U, 235U, 239Pu and 241Pu at 4% each fuel to increase the initial fission chain until it is self-sustained. The purpose is to compare the cross sections from the different ENDLs and find the most suitable ones. The results show that in the case of any application, the difference between ENDF/B, JEFF, JENDL and RUSFOND libraries are in a reliable interval.
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Authors
Carlos E. Velasquez, Claubia Pereira, Maria Auxiliadora F. Veloso, Antonella L. Costa,