Large Sample Neutron Activation Analysis of Ceramic Matrix Composites


Published: Mar 8, 2019
Keywords:
Neutron Activation Analysis Large Sample Ceramic Matrix Composites
I. E. Stamatelatos
T. Vasilopoulou
E. Tsompopoulou
M. Blaauw
K. Mergia
Abstract

Carbon fiber reinforced SiC ceramic matrix composites (Cf/SiC) are promising structural materials for a variety of high-temperature aerospace and energy applications. Since the matrix elements are carbon and silicon, they present low activation after neutron irradiation and therefore are materials of particular interest for fusion energy technology applications. Large Sample Neutron Activation Analysis (LSNAA) was applied to determine the elemental composition of Cf/SiC specimens joined together using a high temperature graphite based adhesive. The neutron irradiations and gamma ray measurements were performed at the BISNIS facility of the Hoger Onderwijs Reactor, TU Delft. The results of this study demonstrate the feasibility of application of LSNAA as a cost-effective method for non-destructive elemental composition analysis of whole ceramic specimens enabling the calculation of induced activity and dose rate after irradiation in different neutron spectra.

Article Details
  • Section
  • Poster contributions
References
I.E. Stamatelatos, K. Mergia, G. Lefkopoulos, R. Forrest, Nucl. Instr. Meth. B, 213 (2004) 511– 514
T. Nozawa, T. Hinoki, A. Hasegawa, et al., J. Nucl. Mat., 386-388 (2009) 622-627
R. Andreani, E. Diegele, W. Gulden, et al., Fus. Eng. Des., 81 (2006) 25-32
R. M. W. Overwater, P. Bode, J. J. M. De Goeij, J. E. Hoogenboom, Anal. Chem. 68 (1996) 341-348
G. Motz, S. Schmidt and S. Beyer, in W. Krenkel (Ed.), The PIP-process: Precursor Properties and Applications, Ceramic Matrix Composites, W. Krenkel Ed., May 2008, Germany, WileyVCH, 2008, 165-186
X. Hernandez, C. Jiménez, K. Mergia, P. Yialouris, V. Liedtke, C. Wilhelmi, S. Messoloras and J. Barcena, J. Mater. Sci. Eng. 2014 (in press)
R. M. W. Overwater, J. E. Hoogenboom, Nucl. Sc. Eng. 117 (1994) 141-157
P. Bode, R. M. W. Overwater, J. J. M. De Goeij, J. Radioanal. Nucl. Chem. 216 1 (1997) 5-11
X-5 Monte Carlo Team, MCNP - A General Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987, April 2003
P. F. Rose, Compiler and Editor, ENDF-201, ENDF/B-VI Summary Documentation, BNLNCS-17541, Brookhaven National Laboratory, October 1991
I. E. Stamatelatos, F. Tzika, T. Vasilopoulou, M. J. J. Koster-Ammerlaan, J. Radioanal. Nucl. Chem. 283 (2010) 735–740
R.A. Forrest, et al., FISPACT 2007 user manual, UKAEA FUS 534 report, March 2007
C.B.A. Forty, J. Nucl. Mat., 283-287 (2000) 1443-1447