Improved performance of U-Mo dispersion fuel by Si addition in Al matrix.

Kim, Y S; Hofman, G.L.

doi:10.2172/1018916

Cited by 6 publications

(4 citation statements)

References 37 publications

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“…Positive results with important reductions in the IL formation thanks to Si were observed by microstructural examinations [24,[25][26][27][28][29][30][31][32], as illustrated in Fig. 3, and confirmed by results obtained internationally [20,[33][34][35][36].…”

Section: -2011: Iris-3 Iris-tum and E-future Si Addition To Al To Mit...supporting

confidence: 56%

Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors

Sannen

Berghe

Leenaers

2014

Advances in Science and Technology

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Historically, uranium enriched to >90% 235U has been used for many peaceful applications requiring high fission densities such as driver fuels for research reactors. However, the use of high-enriched uranium or HEU (all enrichments >20% 235U are considered HEU) for civil applications, is considered a proliferation concern. Since the 1970's, efforts are being devoted to the conversion of research reactors operating on HEU to alternative fuels using uranium with enrichment below 20% or LEU. These efforts imply the development of high-density LEU fuels to replace the low volume-density (mostly) UAlx based HEU fuels. The paper updates the present status of these developments focusing on the UMo dispersion fuel. It aims to provide an overview of the knowledge generated and the lessons learned in roughly 15 years of UMo dispersion fuel R&D in Europe through irradiation experiments and post-irradiation examinations (PIE).

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Section: -2011: Iris-3 Iris-tum and E-future Si Addition To Al To Mit...supporting

confidence: 56%

Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors

Sannen

Berghe

Leenaers

2014

Advances in Science and Technology

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“…High U-loading has a significant effect that limits the full use of the advantage of Si addition. For a practical purpose, the addition of at least 4% as-fabrication Si content appears to be necessary for U-loading greater than 8 gU/cm 3 [46][47]. The results similar to RERTR of U.S. were obtained from other country irradiation tests [48][49][50].…”

Section: The Results Of Irradiation Testmentioning

confidence: 61%

“…Subsequent investigations concerning the addition of Si to Al matrix were also reported [37].It is anticipated that silicon additions to the matrix will inhibit excessive reaction layer formation and improve fuel irradiation performance under high-power operation. As a remedy for reducing reaction between UMo and Al in U-Mo/Al dispersion fuel, adding other alloying element such as Zr , Ti,V,and Nb in UMo has been proposed [56][57][58].…”

Section: Advanced Materials and Structuresmentioning

confidence: 99%

The Development of UMo/Al Dispersion Fuel

Liu

Qian

Lu³

2011

AMR

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UMo/Al dispersion fuel is one of the prospective materials as a high uranium density fuel for high performance research reactors due to its excellent stability during irradiation. In this paper, An overview is provided of current development activities of UMo/Al dispersion fuel at abroad and home, including: the development reasons, this fuel fabrication technology, and the irradiation test. A comprehensive summary is given on the irradiation test, the existing problems and the solution recently obtained by the different countries. Early irradiation experiments with uranium alloys showed promise of acceptable irradiation behavior if these alloys could be maintained in their cubic γ-U crystal structure. The further development of this fuel was delayed due to an unacceptable volume expansion caused by UMo/Al interaction layer (IL) formation and a subsequent gross pore formation at the interface between UMo particles and matrix Al when severe irradiation conditions are reached. In order to alleviate or eliminate the swelling of UMo/Al dispersion fuel,several potential remedies are available to correct the swelling problems. These range from relatively minor changes to the fuel and matrix chemistry, to replacement of the aluminum matrix with another material, or to eliminate the matrix altogether. All of these variations are currently being investigated in the world.

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“…Fewer measures are available to control interaction layer formation and growth during irradiation. An empirical correlation to predict interaction layer growth (Y, µm) as a function of effective fission density rate (݂ ሶ , fissions cm -3 sec -1 ), irradiation time (t, sec), and temperature (T, K) is provided in Equation 6 [21,22].…”

Section: Discussionmentioning

confidence: 99%

Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel

Burkes

Casella

Huber

2015

Journal of Alloys and Compounds

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The Global Threat Reduction Initiative Program continues to develop existing and new test reactor fuels to achieve the maximum attainable uranium loadings to support the conversion of a number of the world's remaining high-enriched uranium fueled reactors to low-enriched uranium fuel. Currently, the program is focused on assisting with the development and qualification of a fuel design that consists of a uranium-molybdenum (U-Mo) alloy dispersed in an aluminum matrix. Thermal conductivity is an important consideration in determining the operational temperature of the fuel and can be influenced by interaction layer formation between the dispersed phase and matrix, porosity that forms during fabrication of the fuel plates or rods, and upon the concentration of the dispersed phase within the matrix. This paper develops and validates a simple model to study the influence of interaction layer formation, dispersed particle size, and volume fraction of dispersed phase in the matrix on the effective conductivity of the composite. The model shows excellent agreement with results previously presented in the literature. In particular, the thermal conductivity of the interaction layer does not appear to be as important in determining the effective conductivity of the composite, while formation of the interaction layer and subsequent consumption of the matrix reveals a rather significant effect. The effective thermal conductivity of the composite can be influenced by the dispersed particle distribution by minimizing interaction layer formation and preserving the higher thermal conductivity matrix.

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Improved performance of U-Mo dispersion fuel by Si addition in Al matrix.

Cited by 6 publications

References 37 publications

Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors

Status of the Low Enriched Uranium Fuel Development for High Performance Research Reactors

The Development of UMo/Al Dispersion Fuel

Modeling the influence of interaction layer formation on thermal conductivity of U–Mo dispersion fuel

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