Open AccessAdvanced Neutron Source Reactor thermal analysis of fuel plate defects
Author(s) -
G.E. Giles
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/220449
Subject(s) - nuclear engineering , nuclear reactor core , research reactor , nuclear reactor , neutron flux , core (optical fiber) , neutron , computer science , environmental science , nuclear physics , process engineering , engineering , physics , telecommunications
The Advanced Neutron Source Reactor (ANSR) is a research reactor designed to provide the highest continuous neutron beam intensity of any reactor in the world. The present technology for determining safe operations were developed for the High Flux Isotope Reactor (HFIR). These techniques are conservative and provide confidence in the safe operation of HFIR. However, the more intense requirements of ANSR necessitate the development of more accurate, but still conservative, techniques. This report details the development of a Local Analysis Technique (LAT) that provides an appropriate approach. Application of the LAT to two ANSR core designs are presented. New theories of the thermal and nuclear behavior of the U{sub 3}Si{sub 2} fuel are utilized. The implications of lower fuel enrichment and of modifying the inspection procedures are also discussed. Development of the computer codes that enable the automate execution of the LAT is included