Graphite Technology Development Plan

Windes, W. ; Burchell, T. ; Bratton, R.

Idaho National Laboratory

关键词: Very High Temperature Reactor;    Reactor Safety;    Simulation Ngnp;    Ngnp;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/968671
RP-ID  :  INL/EXT-07-13165
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  968671

美国|英语

来源: UNT Digital Library

【 摘 要 】

This technology development plan is designed to provide a clear understanding of the research and development direction necessary for the qualification of nuclear grade graphite for use within the Next Generation Nuclear Plant (NGNP) reactor. The NGNP will be a helium gas cooled Very High Temperature Reactor (VHTR) with a large graphite core. Graphite physically contains the fuel and comprises the majority of the core volume. Considerable effort will be required to ensure that the graphite performance is not compromised during operation. Based upon the perceived requirements the major data needs are outlined and justified from the perspective of reactor design, reatcor performance, or the reactor safety case. The path forward for technology development can then be easily determined for each data need. How the data will be obtained and the inter-relationships between the experimental and modeling activities will define the technology development for graphite R&D. Finally, the variables affecting this R&D program are discussed from a general perspective. Factors that can significantly affect the R&D program such as funding, schedules, available resources, multiple reactor designs, and graphite acquisition are analyzed.