Dual phase MgO–ZrO2 ceramics for use in LWR inert matrix fuel

Medvedev, Pavel; Frank, S. M.; O’Holleran, T. P.; Meyer, M. K.

doi:10.1016/j.jnucmat.2005.03.017

Cited by 51 publications

(30 citation statements)

References 6 publications

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“…The host matrix was assumed to be a 1:1 mixture of MgO and ZrO 2 . Such a mixture is expected to have good mechanical and thermal properties [Medvedev et al 2005]. National and international research efforts aiming at the development of suitable fertile free fuel matrix materials are still ongoing, which implies that other fertile free fuel concepts or materials may be found preferable to those used in the current analysis.…”

Section: Computational Methods and Benchmarkingmentioning

confidence: 99%

High Performance Fuel Desing for Next Generation Pressurized Water Reactors

Kazimi¹,

Hejzlar²

2006

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Section: Computational Methods and Benchmarkingmentioning

confidence: 99%

High Performance Fuel Desing for Next Generation Pressurized Water Reactors

Kazimi¹,

Hejzlar²

2006

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“…The equation that calculated the average grain size of the primary phase is given by (5) where M is the magnification of the micrograph.…”

Section: Grain Size Measurementsmentioning

confidence: 99%

“…Since the hydrothermal corrosion rate depends on the exposure area of the sample, the mass loss of the pellet is normalized by the geometric area and is referred as the normalized mass loss (NML). 5,47 The pellet diameter, thickness and weight after every run were recorded after the hydration product was washed off and the NML was calculated by the following equation: (12) where A(t) is geometric area of the sample at time t, m 0 is the initial sample mass, and m(t) is the sample mass at time t. It is worth noting that the hydration product which remains in the open pores in the composites may not be washed and wiped off, thus causing errors in the mass loss measurement. However, comparing with the volume of hydration product layer attached to the surface of composite, the volume of open pores can be neglected, and the measured mass loss is a good estimate for the corrosion process.…”

Section: Hydrothermal Corrosion Of the Compositesmentioning

confidence: 99%

“…1,2 Magnesium oxide (MgO) is a promising candidate for inert matrix (IM) materials due to its high melting point (2827 °C) 2 , high thermal conductivity (13 W/K·m at 1000 °C) 2 , good neutronic properties, and irradiation stability 3,4 However, MgO reacts with water and hydrates easily, which prevents it from being used in light water reactors (LWRs) as an IM. To improve the hydration resistance of MgO-based inert matrix materials, Medvedev 5 and coworkers have recently investigated the introduction of a secondary phase that acts as a hydration barrier. An MgO-ZrO 2 composite was specifically studied and the results showed that the composite exhibited improved hydration resistance than pure MgO.…”

Section: Introductionmentioning

confidence: 99%

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Neri Final Technical Report, De-Fc07-O5id14647, Optimization of Oxide Compounds for Advanced Inert Matrix Materials

Nino¹

2009

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The following is a technical report summarizing all the procedures, experiments, simulations and technical findings of this NERI project. For additional information, details or technical questions regarding this project, please contact jnino@mse.ufl.edu MgO and NDZ......................................................................69 8.4. Grain Size Dependence of MgO and NDZ Polycrystal Thermal Conductivity75 8.5 2009 Composite Processing and Characterization IntroductionIn order to reduce the current excesses of plutonium (both weapon grade and reactor grade) and other transuranium elements, a concept of inert matrix fuel (IMF) has been proposed for an uranium free transmutation of fissile actinides which excludes continuous uranium-plutonium conversion in thermal reactors and advanced systems. 1,2 Magnesium oxide (MgO) is a promising candidate for inert matrix (IM) materials due to its high melting point (2827 °C) 2 , high thermal conductivity (13 W/K·m at 1000 °C) 2 , good neutronic properties, and irradiation stability 3,4 However, MgO reacts with water and hydrates easily, which prevents it from being used in light water reactors (LWRs) as an IM. To improve the hydration resistance of MgO-based inert matrix materials, Medvedev 5 and coworkers have recently investigated the introduction of a secondary phase that acts as a hydration barrier. An MgO-ZrO 2 composite was specifically studied and the results showed that the composite exhibited improved hydration resistance than pure MgO. However, ZrO 2 is insoluble in most acids except HF, which is undesirable for fuel reprocessing. Moreover, the thermal conductivity of ZrO 2 is low and typically less than 3 W·m at 1000 °C. 6 In search for an alternative composite strategy, Nd 2 Zr 2 O 7 , an oxide compound with pyrochlore structure, has been proposed recently as a corrosion resistant phase, and MgO-Nd 2 Zr 2 O 7 composites have been investigated as potential IM materials. at 1000 °C for the MgO-Nd 2 Zr 2 O 7 composite with 90 vol% MgO was recently calculated and reported. 8,9 Other simulations proposed that the MgO-pyrochlore composites could exhibit higher radiation stability than previously reported. 10 Final optimization of the composite microstructure was performed on the 70 vol% MgONd 2 Zr 2 O 7 composite that burnup calculations had shown to have the closest profile to that of MOX fuel. Theoretical calculations also indicated that a homogeneous 70 vol% MgO composite could achieve the desired microstructure that would result in satisfying the dual requirements of good thermal properties. Experimental Procedures Composite Synthesis Solid State Synthesis of Nd 2 Zr 2 O 7Stoichiometric ratios of Nd 2 O 3 (Alfa Aesar 99.9%) and ZrO 2 (99.7%) were added to spherical 3 mm and 10 mm yttria stabilized zirconia (YSZ) milling media in a PTFE (polytetrafluoroethylene) ball mill jar with 100 ml of deionized water and 3 ml of ammonium polyacrylate dispersant (20 vol% Darvan 821A in deionized water). The slurry was milled for 24 hours on the ball mill at 85 rpm ...

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“…Unfortunately, high transuranic content can result in a high power density. This presents a particular problem for a zirconium dioxide based fuel because of the material's low coefficient of thermal conductivity [21,22].…”

Section: Introductionmentioning

confidence: 99%

Effect of Burnable Absorbers on Inert Matrix Fuel Performance and Transuranic Burnup in a Low Power Density Light-Water Reactor

Recktenwald

Deinert

2013

Energies

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Zirconium dioxide has received particular attention as a fuel matrix because of its ability to form a solid solution with transuranic elements, natural radiation stability and desirable mechanical properties. However, zirconium dioxide has a lower coefficient of thermal conductivity than uranium dioxide and this presents an obstacle to the deployment of these fuels in commercial reactors. Here we show that axial doping of a zirconium dioxide based fuel with erbium reduces power peaking and fuel temperature. Full core simulations of a modified AP1000 core were done using MCNPX 2.7.0. The inert matrix fuel contained 15 w/o transuranics at its beginning of life and constituted 28% of the assemblies in the core. Axial doping reduced power peaking at startup by more than ~23% in the axial direction and reduced the peak to average power within the core from 1.80 to 1.44. The core was able to remain critical between refueling while running at a simulated 2000 MWth on an 18 month refueling cycle. The results show that the reactor would maintain negative core average reactivity and void coefficients during operation. This type of fuel cycle would reduce the overall production of transuranics in a pressurized water reactor by 86%.

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Dual phase MgO–ZrO2 ceramics for use in LWR inert matrix fuel

Cited by 51 publications

References 6 publications

High Performance Fuel Desing for Next Generation Pressurized Water Reactors

High Performance Fuel Desing for Next Generation Pressurized Water Reactors

Neri Final Technical Report, De-Fc07-O5id14647, Optimization of Oxide Compounds for Advanced Inert Matrix Materials

Effect of Burnable Absorbers on Inert Matrix Fuel Performance and Transuranic Burnup in a Low Power Density Light-Water Reactor

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