Neutron irradiation damage in MgO, Al2O3 and MgAl2O4 ceramics

Clinard, F.W.; Hurley, G.F.; Hobbs, Linn W.

doi:10.1016/0022-3115(82)90538-4

Cited by 280 publications

(111 citation statements)

References 35 publications

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“…[89][90][91][92][93] The mechanisms underlying the radiation resistance of the spinel structure have been determined as cation disorder (anti-site defects 10 ) and interstitial-vacancy (i-v) recombination. 94 Moreover, MgAl 2 O 4 is a complex oxide compound with two types of cations in the structure.…”

Section: Introductionmentioning

confidence: 99%

“…It has been suggested that this multi-component chemistry suppresses the nucleation and growth of interstitial dislocation loops during irradiation. 90 However, MgAl 2 O 4 has failed in the in-pile studies due to large swelling, mainly as a consequence of irradiation damage by fission products, and thus excludes it from utilization as an IM material. 95,96 The in-pile studies also suggest that the damage mechanisms which involve fission products can be much different from the damage mechanisms described above.…”

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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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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

Nino¹

2009

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“…Important geological applications are related with nuclear waste management, e.g. synthetic ceramic processing of highlevel waste (HLW) in ceramic waste forms and the planned storage of HLW in stable geological formations [1,2]. In Europe these formations are rock salt (NaCl), clay and granite.…”

Section: Introductionmentioning

confidence: 99%

“…It is also a model material, which has been studied systematically [2±8], and its fundamental properties can be used to understand the radiation stability of many other ionic systems. Aluminum oxide, aAl 2 O 3 , is another important ionic material [1,9,10], which will be considered in some detail in order to obtain a more general understanding of the void formation mechanisms in ionic materials.…”

Section: Introductionmentioning

confidence: 99%

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New mechanism for radiation defect production and aggregation in crystalline ceramics

Dubinko

Turkin

Vainshtein

et al. 2001

Journal of Nuclear Materials

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The potential for gas-cooled reactor development

Nuwayhid

Goddard

1995

Int. J. Energy Res.

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Gas‐cooled reactors (GCR) are currently fighting for survival in a world now nearly completely committed to light water reactors (LWR). If some core nuclear design features could be simplified or improved while maintaining their already well‐known safety attractions. GCRs would be able to compete better with other classes of reactors. This would be even more true if their economics could be improved by considering gas‐cooled fast breeder designs. A serious study of these possibilities may conclude once and for all whether simple gas‐cooled reactors of current technological standing can be designed. It is suggested that the next step could be a down‐rated gas‐cooled breeder using AGR component technology while available. A safety enforcing variant of this would admit some ‘diluent’ such as alumina into the core to act as an emergency transient heat sink as well as to increase the doppler coefficient.

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Neutron irradiation damage in MgO, Al2O3 and MgAl2O4 ceramics

Cited by 280 publications

References 35 publications

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

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

New mechanism for radiation defect production and aggregation in crystalline ceramics

The potential for gas-cooled reactor development

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