AGC-2 Graphite Pre-irradiation Data Package

David Swank ; Joseph Lord ; David Rohrbaugh ; William Windes

关键词: CREEP;    DESIGN;    GRAPHITE;    IRRADIATION;    NEUTRON FLUENCE;    PERFORMANCE;    TEST REACTORS AGC-2;    characherization;    NGNP;   

DOI  :  10.2172/991897
RP-ID  :  INL/EXT-10-19588
PID  :  OSTI ID: 991897
Others  :  TRN: US1007649

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The NGNP Graphite R&D program is currently establishing the safe operating envelope of graphite core components for a Very High Temperature Reactor (VHTR) design. The program is generating quantitative data necessary for predicting the behavior and operating performance of the new nuclear graphite grades. To determine the in-service behavior of the graphite for pebble bed and prismatic designs, the Advanced Graphite Creep (AGC) experiment is underway. This experiment is examining the properties and behavior of nuclear grade graphite over a large spectrum of temperatures, neutron fluences and compressive loads. Each experiment consists of over 400 graphite specimens that are characterized prior to irradiation and following irradiation. Six experiments are planned with the first, AGC-1, currently being irradiated in the Advanced Test Reactor (ATR) and pre-irradiation characterization of the second, AGC-2, completed. This data package establishes the readiness of 512 specimens for assembly into the AGC-2 capsule.