AGC-1 Pre-Irradiation Data Report Status

William Windes

关键词: CREEP;    DESIGN;    GRAPHITE;    IRRADIATION;    IRRADIATION CAPSULES;    LICENSING;    PERFORMANCE;    TEST REACTORS AGC-1;    graphite;    NGNP;   

DOI  :  10.2172/1031700
RP-ID  :  INL/EXT-11-23163
PID  :  OSTI ID: 1031700
Others  :  TRN: US1200210

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

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.