Modeling Deep Burn TRISO particle nuclear fuel

Besmann, Theodore M.; Stoller, R.E.; Samolyuk, German D.; Schuck, P. C.; Golubov, S.I.; Rudin, Sven P.; Wills, J. M.; Coe, Joshua D.; Wirth, Brian D.; Kim, S.; Morgan, Dane; Szlufarska, Izabela

doi:10.1016/j.jnucmat.2012.06.041

Cited by 14 publications

(10 citation statements)

References 57 publications

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“…The results have also shown that both polytypes undergo silicidation under vacuum annealing, and that there is formation of ruthenium oxide under air annealing. In actinide oxide fuels, oxygen is released in the fission reaction [1] and therefore will react with Ru as has been demonstrated in this study. Now, what important information can be gleaned from this study which will shed light on the integrity of SiC as a diffusion barrier to fission products in TRISO particles?…”

Section: Discussionmentioning

confidence: 59%

“…The purpose of TRISO fuel configuration is to act as a containing vessel of actinides and fission products so as to reduce the risk of leakage and coolant contamination [1]. The TRISO coated fuel particle is a microsphere which consists of a fuel kernel surrounded by a buffer layer of low density carbon, followed by layers of inner pyrolytic carbon (IpyC), silicon carbide and outer pyrolytic carbon (OpyC).…”

Section: Introductionmentioning

confidence: 99%

“…Each TRISO coating layer has a special function, but SiC is the most important layer that provides most of the structural strength and dimensional stability and acts as the main barrier of metallic fission products. Metals such as ruthenium (Ru), rhodium, palladium, molybdenum, technicium and silver are produced with high yields during fission of uranium and plutonium oxide fuels [1,2]. Minato et al [3] in their experiments on zirconium carbide Triso-coated uranium dioxide fuel particles found a substantial release of 106 Ru when compared to other released fission products of cesium and europium.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Munthali

Theron

Auret

et al. 2014

Journal of Nuclear Materials

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A thin film of ruthenium(Ru) was deposited on n-type 4H-SiC and 6H-SiC by electron beam deposition technique so as to study interface reaction of ruthenium with silicon carbide at various annealing temperatures, and in two annealing environments namely vacuum and air. The Ru-4H-SiC and Ru-6H-SiC films were both annealed isochronally in a vacuum furnace at temperatures ranging from 500 -1000 o C, and the second set of samples were also annealed in air for temperatures ranging from 100 o C to 600 o C. After each annealing temperature, the films were analysed by Rutherford Backscattering spectrometry (RBS). Raman analysis and x-ray diffraction analysis were also used to analyse some of the samples. RBS analysis of 4H-SiC annealed in a vacuum showed evidence of formation of ruthenium silicide (Ru 2 Si 3 ) and diffusion of Ru into SiC starting from annealing temperature of 700 o C going upwards. In the case of Ru-6H-SiC annealed in a vacuum, RBS analysis showed formation of Ru 2 Si 3 at 600 o C, in addition to the diffusion of Ru into SiC at 800 o C . Raman analysis of the Ru-4H-SiC and Ru-6H-SiC samples that were annealed in a vacuum at 1000 o C showed clear D and G carbon peaks which was evidence of formation of graphite . As for the samples annealed in air ruthenium oxidation started at a temperature of 400 o C and diffusion of Ru into SiC commenced at temperatures of 500 o C for both Ru-4H-SiC and Ru-6H-SiC. X-ray diffraction analysis of samples annealed in air at 600 o C showed evidence of formation of ruthenium silicide in both 4H and 6H-SiC but this was not corroborated by RBS analysis.

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Section: Discussionmentioning

confidence: 59%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Munthali

Theron

Auret

et al. 2014

Journal of Nuclear Materials

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“…Excluded are the several codes (e.g. [257,258] to simulate the transport of fission products through coated particles (several different versions of BISO and TRISO particles) using either previously published diffusion coefficient data or fitted data.…”

Section: Silver Diffusionmentioning

confidence: 99%

Diffusion of fission products and radiation damage in SiC

Malherbe

2013

J. Phys. D: Appl. Phys.

109

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A major problem with most of the present nuclear reactors is their safety in terms of the release of radioactivity into the environment during accidents. In some of the future nuclear reactor designs, i.e. Generation IV reactors, the fuel is in the form of coated spherical particles, i.e. TRISO (acronym for Triple Coated Isotropic) particles. The main function of these coating layers is to act as diffusion barriers for radioactive fission products, thereby keeping these fission products within the fuel particles, even under accident conditions. The most important coating layer is composed of polycrystalline 3C-SiC. This paper reviews the diffusion of the important fission products (silver, caesium, iodine and strontium) in SiC. Because radiation damage can induce and enhance diffusion, the paper also briefly reviews damage created by energetic neutrons and ions at elevated temperatures, i.e. the temperatures at which the modern reactors will operate, and the annealing of the damage. The interaction between SiC and some fission products (such as Pd and I) is also briefly discussed. As shown, one of the key advantages of SiC is its radiation hardness at elevated temperatures, i.e. SiC is not amorphized by neutron or bombardment at substrate temperatures above 350°C. Based on the diffusion coefficients of the fission products considered, the review shows that at the normal operating temperatures of these new reactors (i.e. less than 950°C) the SiC coating layer is a good diffusion barrier for these fission products. However, at higher temperatures the design of the coated particles needs to be adapted, possibly by adding a thin layer of ZrC.

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“…There are several factors which may contribute to the failure of the SiC in retaining radioactive FPs. These include; thinning of the SiC layer due to reactions with FPs such as palladium (Pa) and zirconium (Zr) and the gas build up leading to a rise in pressure that may exerts strong tensile stress in the SiC and lead to cracks through which the FPs can escape [7][8][9][10][11].…”

Section: Introductionmentioning

confidence: 99%

The effect of thermal annealing in a hydrogen atmosphere on tungsten deposited on 6HSiC

Thabethe

Hlatshwayo

Njoroge

et al. 2016

Vacuum

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Tungsten (W) film was deposited on bulk single crystalline 6H-SiC substrate and annealed in H 2 ambient at temperatures of 700 ºC, 800 ºC and 1000 ºC for 1 hour. The resulting solidstate reactions, phase composition and surface morphology were investigated by Rutherford backscattering spectrometry (RBS), grazing incidence X-ray diffraction (GIXRD) and scanning electron microscopy (SEM) analysis techniques. These results are compared with the vacuum annealed results reported in our earlier work. As-deposited RBS results indicated the presence of W and O 2 in the deposited thin film, the GIXRD showed the presence of W, The SEM micrographs of the as-deposited samples indicated the W thin film had a uniform surface with small grains. Annealing at 800 ºC led to the agglomeration of W grains into clusters making the surface rough.

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Modeling Deep Burn TRISO particle nuclear fuel

Cited by 14 publications

References 57 publications

Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Microstructure evolution and diffusion of ruthenium in silicon carbide, and the implications for structural integrity of SiC layer in TRISO coated fuel particles

Diffusion of fission products and radiation damage in SiC

The effect of thermal annealing in a hydrogen atmosphere on tungsten deposited on 6HSiC

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