Graphite Technology Development Plan

作者: W. Windes , T. Burchell , M.Carroll

DOI: 10.2172/993160

关键词: Next Generation Nuclear PlantVery-high-temperature reactorPlan (drawing)Nuclear graphiteGraphiteNuclear engineeringReactor safetyTechnology developmentHelium gasWaste managementMaterials science

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

参考文章(9)
J.H.W. Simmons, RADIATION DAMAGE IN GRAPHITE Radiation Damage in Graphite#R##N#International Series of Monographs in Nuclear Energy. pp. 243- ,(1965) , 10.1016/B978-0-08-013753-7.50018-2
TIMOTHY D. BURCHELL, CHAPTER 13 – Fission Reactor Applications of Carbon Carbon Materials for Advanced Technologies. pp. 429- 484 ,(1999) , 10.1016/B978-008042683-9/50015-7
T Burchell, R Bratton, W Windes, NGNP Graphite Selection and Acquisition Strategy Office of Scientific and Technical Information (OSTI). ,(2007) , 10.2172/921767
Linn W. Hobbs, Frank W. Clinard, Steven J. Zinkle, Rodney C. Ewing, Radiation effects in ceramics Journal of Nuclear Materials. ,vol. 216, pp. 291- 321 ,(1994) , 10.1016/0022-3115(94)90017-5
T.D. Burchell, W.P. Eatherly, J.M. Robbins, J.P. Strizak, The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials Journal of Nuclear Materials. ,vol. 191, pp. 295- 299 ,(1992) , 10.1016/S0022-3115(09)80053-6
T.D. Burchell, W.P. Eatherly, The effects of radiation damage on the properties of GraphNOL N3M Journal of Nuclear Materials. pp. 205- 208 ,(1991) , 10.1016/0022-3115(91)90062-C
W V Goeddel, J N Siltanen, Materials for High-Temperature Nuclear Reactors Annual Review of Nuclear Science. ,vol. 17, pp. 189- 250 ,(1967) , 10.1146/ANNUREV.NS.17.120167.001201
T D Burchell, Barry Marsden, R Bratton, Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTS) In: Vol. 5 Graphite PIRT, USNRC, NUREG/CR-6944, Vol. 5, ORNL/TM-2007/147, Vol 5: Vol. 5 Graphite PIRT, USNRC, NUREG/CR-6944, Vol. 5, ORNL/TM-2007/147, Vol 5; 2008.. ,(2008)