TRISO fuel volume fraction and homogeneity: a nondestructive characterization

被引:5
作者
Devi, K. V. Vrinda [1 ]
Dubey, J. N. [1 ]
Gupta, Jyoti [1 ]
Shaikh, I. H. [1 ]
机构
[1] Bhabha Atom Res Ctr, Radiomet Div, Mumbai, Maharashtra, India
关键词
TRISO; Volume fraction; Homogeneity; Radiography; HTR; PARTICLES; FEATURES; DESIGN;
D O I
10.1007/s41365-019-0573-7
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A new nondestructive method to estimate the volume fraction and homogeneity of tristructural isotropic (TRISO)-coated fuel particles in fuel compacts designed for high-temperature reactors has been developed using image analysis of conventional X-radiographs. The method is demonstrated on surrogate fuel compacts containing TRISO-coated particles with kernels made of zirconium dioxide. The methodology incorporates a correction for superimposed images of TRISO particles such that a single X-ray image obtained in any one random orientation is sufficient to characterize the fuel compact in terms of volume fraction and homogeneity. The method is based on the virtual segregation of images of each particle inside the compact with the aid of a calibration standard.
引用
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页数:7
相关论文
共 14 条
[1]  
[Anonymous], 2010, IAEATECDOC1645
[2]   DESIGN OF COATED FUEL-PARTICLES FOR A HYBRID FUSION-FISSION SYSTEM [J].
BULLOCK, RE .
NUCLEAR ENGINEERING AND DESIGN, 1980, 61 (03) :331-345
[3]   Latest achievements of CEA and AREVA NP on HTR fuel fabrication [J].
Charollais, Francois ;
Perrais, Christophe ;
Moulinier, Dominique ;
Perez, Marc ;
Vitali, Marie-Pierre .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (11) :2854-2860
[4]  
Devi K. V. Vrinda, 2015, E J NONDESTR TEST ND
[5]  
Dubey J. N., 2012, P INT C CHAR QUAL CO, V152
[6]   High temperature reactors [J].
Dulera, I. V. ;
Sinha, R. K. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 383 (1-2) :183-188
[7]   Qualification of HTR pebbles by X-ray tomography and thermal analysis [J].
Hania, P. R. ;
Janssen, B. ;
Fedorov, A. V. ;
Knol, S. ;
de Groot, S. ;
Metten, L. ;
van de Sande, A. ;
Futterer, M. A. .
NUCLEAR ENGINEERING AND DESIGN, 2012, 251 :47-52
[8]  
Hubbell J. H., TABLES XRAY MASS ATT, DOI [10.18434/T4D01F, DOI 10.18434/T4D01F]
[9]   THE HELIUM-COOLED HIGH-TEMPERATURE REACTOR IN THE FEDERAL-REPUBLIC-OF-GERMANY - SAFETY FEATURES, INTEGRITY CONCEPT, OUTLOOK FOR DESIGN CODES AND LICENSING PROCEDURES [J].
NICKEL, H ;
HOFMANN, K ;
WACHHOLZ, W ;
WEISBRODT, I .
NUCLEAR ENGINEERING AND DESIGN, 1991, 127 (02) :181-190
[10]   Recovery and recycling of uranium from rejected coated particles for compact high temperature reactors [J].
Pai, Rajesh V. ;
Mollick, P. K. ;
Kumar, Ashok ;
Banerjee, J. ;
Radhakrishna, J. ;
Chakravartty, J. K. .
JOURNAL OF NUCLEAR MATERIALS, 2016, 473 :229-236