Browse > Article
http://dx.doi.org/10.1016/j.net.2021.12.003

Front-end investigations of the coated particles of nuclear fuel samples - ion polishing method  

Krajewska, Zuzanna M. (National Centre for Nuclear Research)
Buchwald, Tomasz (Poznan University of Technology, Institute of Materials Research and Quantum Engineering)
Tokarski, Tomasz (Academic Centre for Materials and Nanotechnology, AGH University of Science and Technology)
Gudowski, Wacław (National Centre for Nuclear Research)
Publication Information
Nuclear Engineering and Technology / v.54, no.6, 2022 , pp. 1935-1946 More about this Journal
Abstract
The investigations of the coated-particles of nuclear fuel samples are carried out in three stages: front-end, irradiation in the reactor core, and post-irradiation examination. The front-end stage is the initial analysis of the failures rates of produced samples before they are placed in the reactor core. The purpose of the verification is to prepare the particles for an experiment that will determine the degree of damage to the coated particles at each stage. Before starting experiments with the samples, they must be properly prepared. Polishing the samples in order to uncover the inner layers is an important, initial experimental step. The authors of this paper used a novel way to prepare samples for testing - by applying an ion polisher. Mechanical polishing used frequently for sample preparations generates additional mechanical damages in the studied fuel particle, thus directly affecting the experimental results. The polishing methods were compared for three different coated particles using diagnostic methods such as Raman spectroscopy, scanning electron microscopy, and confocal laser scanning microscopy. Based on the obtained results, it was concluded that the ion polishing method is better because the level of interference with the structures of the individual layers of the tested samples is much lower than with the mechanical method. The same technique is used for the fuel particles undergone ion implantation simulating radiation damage that can occur in the reactor core.
Keywords
TRISO particle; Raman spectroscopy; Polishing methods; Roughness profile;
Citations & Related Records
연도 인용수 순위
  • Reference
1 A. Sowder, C. Marciulescu, Uranium Oxycarbide (UCO) Tristructural Isotropic (TRISO) Coated Particle Fuel Performance, Topical Report EPRI-AR-1 (NP), Technical Report, 2019.
2 P.A. Demkowicz, D. Marshall, J. Palmer, G. Hawkes, J. Sterbentz, TRISO fuel experience and capabilities in the DOE advanced gas reactor program, ART INL, in: GAIN-EPRI-NEI Advanced Fuels Workshop March 5-6, Boise State University, 2019.
3 H.X. Xu, J. Lin, J.J. Li, Z.Y. Zhu, G.L. Zeng, J.D. Liu, B.C. Gu, B. Liu, Characterization the microstructure and defects of matrix graphite irradiated with Xe ions, Nucl. Instrum. Methods Phys. Res. B 406 (2017) 638-642.   DOI
4 H.J. Sarmah, D. Mohanta, Emergence of Raman active D- band and unusually suppressed conductivity mediated by nanoscale defects in pencil-lead graphitic systems under 80 keV Xe+ ion irradiation, Nucl. Instrum. Methods Phys. Res. B 463 (2020) 1-6.   DOI
5 C.M. Efaw, J.L. Vandegrift, M. Reynolds, S. McMurdie, B.J. Jaques, H. Hu, H. Xiong, M.F. Hurley, Characterization of zirconium oxides part I: Raman mapping and spectral feature analysis, Nucl. Mater. Energy 21 (2019) 100707.   DOI
6 M. Couzi, J.-L. Bruneel, D. Talaga, L. Bokobza, A multi wavelength Raman scattering study of defective graphitic carbon materials: the first order Raman spectra revisited, Carbon 107 (2016) 388-394.   DOI
7 K. Verfondern, H. Nabielek, M.J. Kania, H.J. Allelein, High-Quality Thorium TRISO Fuel Performance in HTGRs, Forschungszentrum Juelich, 2013.
8 NGNP, Fuel Qualification White Paper, INL, INL/EXT-10-17686, 2010.
9 D. Helary, O. Dugne, X. Bourrat, Advanced characterization techniques for SiC and PyC coatings on high-temperature reactor fuel particles, J. Nucl. Mater. 373 (2008) 150-156.   DOI
10 High Temperature, High Temperature Gas Cooled Reactor Fuels and Materials, IAEA-TECDOC-1645, 2010.
11 P.A. Demkowicz, B. Liu, J.D. Hunn, Coated particle fuel: historical perspectives and current progress, J. Nucl. Mater. 515 (2019) 434-450.   DOI
12 H. Wu, R. Gakhar, A. Chen, S. Lam, C.P. Marshall, R.O. Scarlat, Comparative analysis of microstructure and reactive sites for nuclear graphite IG-110 and graphite matrix A3, J. Nucl. Mater. 528 (2020) 151802.   DOI
13 J. Wang, An Integrated Performance Model for High Temperature Gas Cooled Reactor Coated Particle Fuel, Massachusetts Institute of Technology, 2004.
14 G.W. Helmreich, J.D. Hunn, J.W. McMurray, R.D. Hunt, B.C. Jolly, M.P. Trammell, D.R. Brown, B.J. Blamer, T.J. Reif, H.T. Kim, Year One Summary of X-Energy Pebble Fuel Development at ORNL, ORNL/TM-2017/337, 2017.
15 E.S. Kim, Y.W. Kim, Characterization of 3 MeV H+ irradiation induced defects in nuclear grade graphite, Solid State Commun. 150 (2010) 1633-1636.   DOI
16 G. Zheng, P. Xu, K. Sridharan, T. Allen, Characterization of structural defects in nuclear graphite IG-110 and NBG-18, J. Nucl. Mater. 446 (2014) 193-199.   DOI
17 P. B Arberis, T. Merle-Mejean, P. Quintard, On Raman spectroscopy of zirconium oxide films, J. Nucl. Mater. 246 (1997) 232-243.   DOI
18 L.P. Rodriguez Garcia, D.M. Perez, C.R. Garcia Hernandez, D.E. Milian Lorenzo, C.A. Brayner de Oliveira Lira, Development of a Methodology for the Evaluation of the Thermomechanical Behavior of the TRISO Fuel, INAC, 2017.
19 M.R. Ammar, N. Galy, J.N. Rouzaud, N. Toulhoat, C.E. Vaudey, P. Simon, N. Moncoffre, Characterizing various types of defects in nuclear graphite using Raman scattering: heat treatment, ion irradiation and polishing, Carbon 95 (2015) 364-373.   DOI
20 O.A. Maslova, M.R. Ammar, G. Guimbretiere, J.N. Rouzaud, P. Simon, Determination of crystallite size in polished graphitized carbon by Raman spectroscopy, Phys. Rev. B 86 (2012) 134205.   DOI