WG-MOX Fuel Zr-tube Neutron Spectrum Comparison in ATR and PWR

Chang, Gray S.

Idaho National Laboratory

关键词: Comparison;    Monte Carlo;    Ineel;    11 - Nuclear Fuel Cycle And Fuel Materials;    Mixed Oxide Fuels;   

DOI  :  10.2172/911215
RP-ID  :  INL/EXT-05-00025
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911215

美国|英语

来源: UNT Digital Library

【 摘 要 】

An experiment containing WG-MOX fuel has been designed and irradiated from 1998 to 2004 in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). Important neutronics parameters were computed using novel Monte Carlo methods. The purpose of this summary is to compare the Weapons-Grade Mixed Oxide fuel (WG-MOX) Zr-tube’s neutron spectrum in ATR and PWR. The results indicate that the Zrtube’s neutron spectrum in ATR are softer than in PWR.