MATERIAL ISSUES FOR CURRENT AND ADVANCED NUCLEAR REACTOR DESIGNS

作者: Jasmina Vujić , Peter Hosemann

DOI: 10.7251/CM.V1I5.1493

关键词: Prolonged exposureMechanical engineeringNuclear reactorCoolantLifetime extensionTemperature and pressureProcess engineeringLead (geology)Current (fluid)Reliability (semiconductor)Materials science

摘要: In all engineering applications, design and materials together determine the functionality reliability of a device. This is particularly important in nuclear systems where are pushed to their limits phenomena not present anywhere else occur. combination high temperature pressure, stress, corrosive environment radiation combined causes significant challenges. Majority commercial LWRs today licensed for 40 years operation, but many them undergo lifetime extension 60 or possibly 80 years. Materials degradation has always been issue. However, due plant extension, finding that could sustain prolonged exposure these extreme conditions become problem. addition challenges current LWRs, advanced reactors usually deal with even more difficult issues operational requirements. Unusual heat transport media, such as liquid metals, salts other types coolants, lead whole new set material While corrosion main issue, much higher operating temperatures create additional difficulties. this paper, we an overview reactor designs.

参考文章(29)
Doonyapong Wongsawaeng, Donald Olander, Liquid-metal bond for LWR fuel rods Nuclear Technology. ,vol. 159, pp. 279- 291 ,(2007) , 10.13182/NT07-A3876
Karl G. E. Brenner, Leslie W. Graham, The Development and Application of a Unified Corrosion Model for High-Temperature Gas-Cooled Reactor Systems Nuclear Technology. ,vol. 66, pp. 404- 414 ,(1984) , 10.13182/NT84-A33443
M.G. Barker, D.J. Wood, THe corrosion of chromium, iron, and stainless steel in liquid sodium Journal of the Less Common Metals. ,vol. 35, pp. 315- 323 ,(1974) , 10.1016/0022-5088(74)90243-4
P. Hosemann, Y. Dai, E. Stergar, H. Leitner, E. Olivas, A. T. Nelson, S. A. Maloy, Large and Small Scale Materials Testing of HT-9 Irradiated in the STIP Irradiation Program Experimental Mechanics. ,vol. 51, pp. 1095- 1102 ,(2011) , 10.1007/S11340-010-9419-2
Masatoshi Kondo, Takuya Nagasaka, Akio Sagara, Nobuaki Noda, Takeo Muroga, Qi Xu, Masaru Nagura, Akihiro Suzuki, Takayuki Terai, Metallurgical study on corrosion of austenitic steels in molten salt LiF–BeF2 (Flibe) Journal of Nuclear Materials. ,vol. 386-388, pp. 685- 688 ,(2009) , 10.1016/J.JNUCMAT.2008.12.317
Jasmina Vujić, Ryan M. Bergmann, Radek Škoda, Marija Miletić, Small modular reactors: Simpler, safer, cheaper? Energy. ,vol. 45, pp. 288- 295 ,(2012) , 10.1016/J.ENERGY.2012.01.078
V.N Shah, C.J Hookham, Long-term aging of light water reactor concrete containments Nuclear Engineering and Design. ,vol. 185, pp. 51- 81 ,(1998) , 10.1016/S0029-5493(98)00187-3
C. Cabet, A. Terlain, P. Lett, L. Guétaz, J.-M. Gentzbittel, High temperature corrosion of structural materials under gas-cooled reactor helium Materials and Corrosion-werkstoffe Und Korrosion. ,vol. 57, pp. 147- 153 ,(2006) , 10.1002/MACO.200503901
Y. Katoh, L.L. Snead, C.H. Henager, A. Hasegawa, A. Kohyama, B. Riccardi, H. Hegeman, Current status and critical issues for development of SiC composites for fusion applications Journal of Nuclear Materials. ,vol. 367, pp. 659- 671 ,(2007) , 10.1016/J.JNUCMAT.2007.03.032