Hostname: page-component-cd9895bd7-dk4vv Total loading time: 0 Render date: 2024-12-25T13:02:00.663Z Has data issue: false hasContentIssue false

SiC Based Neutron Flux Monitors for Very High Temperature Nuclear Reactors

Published online by Cambridge University Press:  01 February 2011

Wolfgang Windl
Affiliation:
[email protected], The Ohio State University, Materials Science and Engineering, 2041 College Rd., Columbus, OH, 43210, United States
Behrooz Khorsandi
Affiliation:
[email protected], The Ohio State University, Nuclear Engineering, Columbus, OH, 43210, United States
Weiqi Luo
Affiliation:
[email protected], The Ohio State University, Materials Science and Engineering, Columbus, OH, 43210, United States
Thomas E. Blue
Affiliation:
[email protected], The Ohio State University, Nuclear Engineering, Columbus, OH, 43210, United States
Get access

Abstract

The Gas Turbine-Modular Helium Reactor (GT-MHR) and the Very-High-Temperature Reactor (VHTR) are next-generation high-temperature reactor types that are being designed to operate under normal conditions with primary coolant outlet temperatures in the range of 850 °C and 1000 °C, respectively. A new type of silicon carbide based diode neutron detector is currently under development in order to monitor the neutron flux in this environment. An important problem, in this context, is the long-time reliability of the diodes under continuous irradiation at high temperatures. In this paper, we discuss a computational methodology to study the accumulation of radiation damage in the detectors as a function of temperature and its influence on the electrical properties.

Type
Research Article
Copyright
Copyright © Materials Research Society 2006

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

[1] Greenwood, L.R., and Smither, R.K., “SPECTER: Neutron Damage Calculations for Materials Irradiations,” ANL/FPP/TM-197, Jan. 1985.Google Scholar
[2] Lee, M.B., and Farnum, E.H., “The Effect of Neutron Energy on Defect Production in Alumina,” Nuclear instruments and Methods in Physics Research, Vol. B, No. 102, 1995, pp. 113118.Google Scholar
[3] Ziegler, F.J., “SRIM-2003,” Nuclear Instruments and Methods in Physics Research, Vol. B, No. 219-220, 2004, pp. 10271036.Google Scholar
[4] Forster, R.A., et al “MCNP Version 5,” Nuclear Instruments and Methods in Physics Research, Vol. B, No. 213, 2004, pp. 8286.Google Scholar
[5] Robinson, M. T., MARLOWE: Binary Collision Cascade Simulation Program, Version 15b, A Guide for Users (December 5, 2002), http://www-rsicc.ornl.gov/codes/psr/psr1/psr-137.html.Google Scholar
[6] Devanathan, R., Weber, W. J. and Gao, F., Atomic scale simulation of defect production in irradiated 3C-SiC, J. Appl. Phys. 90, 2303 (2001).Google Scholar
[7] Evans, M. H., Zhang, X.-G., Joannopoulos, J. D., and Pantelides, S. T., First-Principles Mobility Calculations and Atomic-Scale Interface Roughness in Nanoscale Structures, Phys. Rev. Lett. 95, 106802 (2005).Google Scholar
[8] Kresse, G. and Hafner, J., Phys. Rev. B 47, 558 (1993); 49, 14251 (1994); G. Kresse and J. Furthmüller, Comput. Mater. Sci. 6, 15 (1996); Phys. Rev. B 55, 11169 (1996).Google Scholar
[9] Kresse, G. and Hafner, J., J. Phys.: Condes. Matt. 6, 8245 (1994).Google Scholar