A comparison of four tomographic methods for nuclear fuel pin analysis

Niculae, Carmen; Mateescu, Gheorghe; Turcanu, C.

doi:10.1016/0022-3115(95)00084-4

Cited by 9 publications

(3 citation statements)

References 15 publications

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“…This issue is addressed in Barton (1977); Honda et al (1990) and Craciunescu et al (1995). Neutron interrogation is used in the two former articles, with Barton (1977) comparing differing numbers of angles and projections in ART reconstruction in a feasibility study.…”

Section: Post Processing Techniquesmentioning

confidence: 98%

“…Neither paper provides quantitative data upon which to base their arguments about which technology is more suited to the problem. Unlike Craciunescu et al (1995), here four methods of gamma emission tomography are compared in a simulator to ascertain which is more suited to evaluating burn-up within the fuel. The work presented utilised two phantoms and then simulated the scanning of these phantoms using the following methods: Maximum Likelihood (ML), Maximum Entropy (ME), ART, and Monte Carlo implementation of the Back Projection Technique (MCBP).…”

Section: Post Processing Techniquesmentioning

confidence: 99%

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The use of ionising radiation to image nuclear fuel: A review

Parker

Joyce

2015

Progress in Nuclear Energy

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a b s t r a c tImaging of nuclear fuel using radiation has been carried out for decades for a variety of reasons. Two important reasons are Physical Invertory Verification (PIV) and Quality Assurance (QA). The work covered in this review focuses on the imaging of nuclear fuel using ionising radiation. The fuels investigated are both fresh and spent, composed of assorted materials, and in various physical forms. The radiations used to characterise the nuclear fuel include g, a, b, muons, neutrons and X-rays. The research covered in this review, spans the past four decades and show how the technology has developed over that time. The advancement of computing technology has greatly helped with the progression of the images that are produced. The field began with 2D images in black and white showing the density profiles of g rays from within an object, culminating in 2013 when a pebble bed fuel element was reproduced in 3D showing each 0.5 mm UO 2 globule within it. With the ever increasing computing technology available to the industry, this can only mean an increase in the rate of development of imaging technologies like those covered in this review.

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Section: Post Processing Techniquesmentioning

confidence: 98%

Section: Post Processing Techniquesmentioning

confidence: 99%

The use of ionising radiation to image nuclear fuel: A review

Parker

Joyce

2015

Progress in Nuclear Energy

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“…For example, the implementation of computer tomography, widely used in medical applications, is a noninvasive technique that can be employed successfully in the investigation of single fuel rods as well as entire fuel assemblies. This technique, although not new in nuclear fuel characterisation, [4][5][6][7][8][9] is a growing area due to the continued progress of computer science that makes possible the implementation of more sophisticated and better performing algorithms for the reconstruction of images.…”

Section: Introductionmentioning

confidence: 99%

Nondestructive Determination of Fresh and Spent Nuclear Fuel Rod Density Distributions through Computerised Gamma-Ray Transmission Tomography

Caruso¹,

Murphy²,

Jatuff³

et al. 2008

Journal of Nuclear Science and Technology

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The morphology of single PWR UO 2 fuel rods has been investigated by employing computerised gamma-ray transmission tomography. Four highly burnt fuel rods of different burnups (from 52 GWd/t to 126 GWd/t) and a fresh rod have been investigated. This paper describes the tomographic station built to acquire the projections together with the related experimental procedure, followed by the description of the image reconstruction techniques implemented. The principal results obtained are presented and analysed at three levels. First, the derived linear attenuation coefficient matrix, which is very useful for the implementation of emission tomography, is discussed. Second, the variation of density as a function of rod radius is presented, showing an interesting morphological change of the fuel with burnup. Particularly for the highest burnup sample, the periphery is characterised by a lower density (a steep decrease of almost 10% from the adjacent region) characteristic of an ultrahigh-burnup high-porosity structure. Finally, the nondestructive derivation of the volume-averaged fuel density was performed, compared with other experimental data, and plotted as a function of burnup, so that an interesting linear relationship between density and burnup was established, providing a potential indicator for the noninvasive determination of nuclear fuel rod burnup.

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