Reference Neutron Radiographs of Nuclear Reactor Fuel

Domanus, J. C.

doi:10.1007/978-94-009-3871-7_48

Cited by 5 publications

(2 citation statements)

References 2 publications

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“…Whereas the inspection of activated samples is not very new and has been performed at different places [3,12], state of the art detectors with the ability for digitising should be applied now to be able to use methods of post-processing and quantification of the obtained images.…”

Section: Technical Solution and Experimental Proceduresmentioning

confidence: 99%

The Investigation of Highly Activated Samples by Neutron Radiography at the Spallation Source Sinq

Lehmann

Vontobel

Wiezel

2001

Nondestructive Testing and Evaluation

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In addition to conventional radiography investigations there is a demand to inspect highly activated samples of spent nuclear fuel or accelerator target materials to detect material defects caused by the strong applied radiation and interaction with the coolant. For this purpose, special facilities and equipment have to be used which are well shielded. Furthermore, neutron radiography detectors have to be found which are insensitive to the radiation emitted by the sample under investigation.The radiography station NEUTRA at PSI can be modified to such a facility to handle highly activated samples under dry conditions and can perform sensitive investigations with high spatial resolution.The paper describes this experimental assembly and shows results from the first cycle of investigations. Several problems (technical and administrative ones) are discussed in some detail.

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Section: Technical Solution and Experimental Proceduresmentioning

confidence: 99%

The Investigation of Highly Activated Samples by Neutron Radiography at the Spallation Source Sinq

Lehmann

Vontobel

Wiezel

2001

Nondestructive Testing and Evaluation

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“…One of the main fields of NR application is the nuclear industry. For example, radiography tests can be conducted for the location of pellets of 235 U in fuel elements intended to contain only 238 U as well as on the crack, swelling, gap size of plug [2]. Using a transfer exposure method, in which the build-up radioactivity of dysprosium(Dy), indium(In) and gold(Au) screens can be subsequently exposed on a film in a dark room, allowing testing of highly radioactive objects, such as irradiated nuclear fuel.…”

Section: Introductionmentioning

confidence: 99%

Measurement of Ballooning Gap Size of Irradiated Fuels Using Neutron Radiography Transfer Method and HV Image Filter

Sim¹,

Kim²,

Oh³

et al. 2013

Journal of the Korean Society for Nondestructive Testing

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ASTM-BPI/SI were used. An activated latent image formed in the 100 μm Dy foil was subsequently transferred in a dark room for more than 8 hours to the SR film which is a maximum of three half-lives. Due to the L/D ratio an unsharpness of 9.82-14 and a magnification of 1.0003 were given. After digitizing an image of SR film, the ballooning gap of the plug was discernible by an H/V filter of image processing. The gap size of the ballooned element, K174L-3, is equal to or greater than 1.2 mm. The development of a transfer method played a pivotal role in developing high burn-up of Wolsung and PWR nuclear fuel type.

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Neutron Radiography of Light Water Reactor Fuel Rods at the High Flux Reactor Petten

Bakker¹,

Baritello²,

Bordo³

et al. 1987

Neutron Radiography

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Reference Neutron Radiographs of Nuclear Reactor Fuel

Abstract: The collection contains 158 neutron radiographs, reproduced on photographic paper (twice enlarged) and on duplicating film (original size).

Cited by 5 publications

References 2 publications

The Investigation of Highly Activated Samples by Neutron Radiography at the Spallation Source Sinq

The Investigation of Highly Activated Samples by Neutron Radiography at the Spallation Source Sinq

Measurement of Ballooning Gap Size of Irradiated Fuels Using Neutron Radiography Transfer Method and HV Image Filter

Neutron Radiography of Light Water Reactor Fuel Rods at the High Flux Reactor Petten

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