FY-2010 AGC-1 Disassembly Preparation

Philip L. Winston

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

DOI  :  10.2172/993183
RP-ID  :  INL/EXT-10-19758
PID  :  OSTI ID: 993183
Others  :  TRN: US1008061

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 Project Graphite Research and Development program is currently establishing the safe operating envelope of graphite core components for a very high temperature reactor 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 fluencies, 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 and preirradiation characterization of the second, AGC-2, completed.