Azimuthal flux distribution measurements around fuel rods in reduced-moderation LWR lattices

作者：Yoshioka Kenichi^*; Kitada Takanori; Nagaya Yasunobu

来源：Progress in Nuclear Energy, 2015, 82: 7-15.

DOI：10.1016/j.pnucene.2014.07.037

• Azimuthal flux measurement
• Foil activation
• Micro reactor physics
• Critical experiment
• Monte Carlo
• MVP

An advanced analysis method named "micro reactor physics approach" was proposed, and the approach is needed for future reactor design considering the neutron behavior in fuel pellets. In order to validate the approach, neutron flux distribution measurements in a fuel pellet should be required. We have measured azimuthal flux distribution of fuel rods in Toshiba Nuclear Critical Assembly (NCA). A foil activation method with metallic foils was used for the measurement. Measured values were analyzed by a continuous energy Monte Carlo code MVP with the JENDL-3.3 library. The measurements are useful for the validation of an advanced fuel design method considering the neutron behavior in fuel pellets.

• 出版日期2015-7