FY-2010 AGC-1 Disassembly Preparation
Description:
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 underw…
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Date:
September 1, 2010
Creator:
Winston, Philip L.
Partner:
UNT Libraries Government Documents Department