Open AccessAGC-1 Pre-Irradiation Data Report Status
Author(s) -
William E. Windes
Publication year - 2011
Language(s) - English
Resource type - Reports
DOI - 10.2172/1031700
Subject(s) - graphite , irradiation , nuclear graphite , nuclear engineering , materials science , nuclear reactor , creep , radiochemistry , nuclear physics , composite material , engineering , chemistry , physics
The Next Generation Nuclear Plant (NGNP) Graphite R&D program is currently measuring irradiated material property changes in several grades of nuclear graphite for predicting their behavior and operating performance within the core of new Very High Temperature Reactor (VHTR) designs. The Advanced Graphite Creep (AGC) experiment consisting of six irradiation capsules will generate this irradiated graphite performance data for NGNP reactor operating conditions. All samples in the experiment will be fully characterized before irradiation, irradiated in the Advanced Test Reactor (ATR), and then re-examined to determine the irradiation induced changes to key materials properties in the different graphite grades. The information generated during the AGC experiment will be utilized for NRC licensing of NGNP reactor designs, shared with international collaborators in the Generation IV Information Forum (GIF), and eventually utilized in ASME design code for graphite nuclear applications. This status report will describe the process the NGNP Graphite R&D program has developed to record the AGC1 pre-irradiation examination data