Quantitative analysis of the fission product distribution in a damaged fuel assembly using gamma-spectrometry and computed tomography for the Phébus FPT3 test

Biard, B.

doi:10.1016/j.nucengdes.2013.05.019

Cited by 10 publications

(5 citation statements)

References 12 publications

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“…Accordingly, such a procedure has so far only been applied at research institutions, e.g. in the measurement of a 21-rod bundle that was subjected to fuel melting and analyzed [29], and in measurements on individual fuel rods [20]. In spite of the small content of fuel material in the latter case, a 60 Co source as strong as 2.4 GBq still had to be used.…”

Section: Discussionmentioning

confidence: 99%

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Svärd

Holcombe

Grape

2015

Nuclear Instruments and Methods in Physics Research Section A:

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a b s t r a c tA fuel assembly operated in a nuclear power plant typically contains 100-300 fuel rods, depending on fuel type, which become strongly radioactive during irradiation in the reactor core. For operational and security reasons, it is of interest to experimentally deduce rod-wise information from the fuel, preferably by means of non-destructive measurements. The tomographic SPECT technique offers such possibilities through its two-step application; (1) recording the gamma-ray flux distribution around the fuel assembly, and (2) reconstructing the assembly's internal source distribution, based on the recorded radiation field. In this paper, algorithms for performing the latter step and extracting quantitative relative rod-by-rod data are accounted for.As compared to application of SPECT in nuclear medicine, nuclear fuel assemblies present a much more heterogeneous distribution of internal attenuation to gamma radiation than the human body, typically with rods containing pellets of heavy uranium dioxide surrounded by cladding of a zirconium alloy placed in water or air. This inhomogeneity severely complicates the tomographic quantification of the rod-wise relative source content, and the deduction of conclusive data requires detailed modelling of the attenuation to be introduced in the reconstructions. However, as shown in this paper, simplified models may still produce valuable information about the fuel.Here, a set of reconstruction algorithms for SPECT on nuclear fuel assemblies are described and discussed in terms of their quantitative performance for two applications; verification of fuel assemblies' completeness in nuclear safeguards, and rod-wise fuel characterization. It is argued that a request not to base the former assessment on any a priori information brings constraints to which reconstruction methods that may be used in that case, whereas the use of a priori information on geometry and material content enables highly accurate quantitative assessment, which may be particularly useful in the latter application.Two main classes of algorithms are covered; (1) analytic filtered back-projection algorithms, and (2) a group of model-based or algebraic algorithms. For the former class, a basic algorithm has been implemented, which does not take attenuation in the materials of the fuel assemblies into account and which assumes an idealized imaging geometry. In addition, a novel methodology has been presented for introducing a first-order correction to the obtained images for these deficits; in particular, the effects of attenuation are taken into account by modelling the response for an object with a homogeneous mix of fuel materials in the image area. Neither the basic algorithm, nor the correction method requires prior knowledge of the fuel geometry, but they result in images of the assembly's internal activity distribution. Image analysis is then applied to deduce quantitative information.Two algebraic algorithms are also presented, which model attenuation in the fuel assemblies to different degrees...

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Section: Discussionmentioning

confidence: 99%

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Svärd

Holcombe

Grape

2015

Nuclear Instruments and Methods in Physics Research Section A:

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“…The detector is a high purity Germanium detector, coupled to an acquisition system. The efficiency correction is made thanks to calibration measurements and efficiency function computation performed with the CAMELIAS tool [23] that was previously developed at the in-pile experimental laboratory of IRSN for the purpose of CABRI and PHEBUS [25] gamma-spectrometry stations. Another lab-made tool called CAPRICE is used for the batch calculation of the gamma spectra, acquired and processed with GENIE 2000 [24].…”

Section: Irismentioning

confidence: 99%

Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program

Biard

Chevalier

Gaillard

et al. 2020

Annals of Nuclear Energy

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The CABRI International Program (CIP) tests irradiated UO2 or MOX fuels submitted to Reactivity Initiated Accidents (RIA) representative power pulses in prototypical PWR thermal-hydraulic conditions. CIP is managed by The Institut de Radioprotection et de Sûreté Nucléaire (IRSN) within a OECD/NEA framework. Experiments are conducted in the CABRI reactor operated by CEA. For CIP, CABRI benefits from a new pressurized water loop. An important refurbishment program enhanced the facility safety and upgraded the experimental equipment such as the nondestructive examination bench IRIS and the Hodoscope on-line fuel motion monitoring system. Specific test devices with appropriate innovative instrumentation follow the test rod behavior during the transient.The successful first test in the pressurized water loop demonstrated the CABRI capability to perform fully instrumented RIA tests in PWR conditions and to provide highly valuable results for RIA phenomena modelling (boiling crisis, post-failure events), for code validation, and for assessing PWR safety criteria. Highlights• The CABRI international Program (CIP) tests industrial irradiated fuel rods in a circulating test loop ensuring prototypical PWR conditions.• The CABRI reactor provides experimental conditions and power pulses representative of PWR RIA transients.• A complete instrumentation is available: online fuel motion monitoring system (Hodoscope), instrumented test device, pre-test and post-test non-destructive examination (IRIS).• Results will help modelling, code qualification and validation, and provide a new technical basis for PWR fuel safety criteria assessment for RIA conditions.

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“…Over 20 years later very similar research is still being carried out [Biard (2013)]. Here emitted g ray measurements along with transmission X-ray computed tomography allowed for fission product distributions to be evaluated.…”

Section: Accident Scenariosmentioning

confidence: 99%

“…Barium distribution throughout a failed FPT3 assembly. Reconstructed using FBP [Biard (2013)]. [Niculae et al (1996)].…”

Section: Improvements To Nuclear Fuelmentioning

confidence: 99%

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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Quantitative analysis of the fission product distribution in a damaged fuel assembly using gamma-spectrometry and computed tomography for the Phébus FPT3 test

Cited by 10 publications

References 12 publications

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies

Reactivity Initiated Accident transient testing on irradiated fuel rods in PWR conditions: The CABRI International Program

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

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