Enhanced Thermal Conductivity Oxide Fuels

Solomon, Abraham; Revankar, Shripad T.; McCoy, J. Kevin

doi:10.2172/862369

Cited by 9 publications

(16 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…There are two fabrication methods, slug bisque (SB) and green granule (GG), developed to produce high thermal conductivity UO 2 -BeO oxide nuclear fuels, namely SB-UO 2 -BeO and GG-UO 2 -BeO fuels as described (Kuchibhotla, 2004;Solomon et al, 2005). These two processing routes generate pellets with two different microstructures.…”

Section: Fabrication Methods Of Enhanced Thermal Conductivity Uo 2 -Bmentioning

confidence: 99%

See 1 more Smart Citation

Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

Zhou

Liu

Revankar

2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

Section: Fabrication Methods Of Enhanced Thermal Conductivity Uo 2 -Bmentioning

confidence: 99%

“…The remainder of the BeO is relatively pure, with only small amounts of porosity. (Solomon et al, 2005). Note that the large amount of small UO 2 particles near the interfaces of the components.…”

Section: Fem Thermal Model Of Sb-uo 2 -Beo Nuclear Fuelsmentioning

confidence: 96%

Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

Zhou

Liu

Revankar

2015

Annals of Nuclear Energy

View full text Add to dashboard Cite

“…al. [36] found that 10 vol.% of continuous phase BeO in UO 2 increases the thermal conductivity of the composite by 50% over standard UO 2 fuel. Furthermore, a 25% increase in thermal conductivity of UO 2 can be obtained at 1100 • K with an almost continuous 4.2 vol.% of BeO phase at the grain boundaries [37].…”

Section: Thermal Conductivity Enhancement In Oxide Based Fuelsmentioning

confidence: 96%

“…Slow heating favors the lower temperature (∼400 • C) curing of the polymer that involves the competitive processes of gas evolution by decomposition of the lighter molecules releasing H 2 and polymerization. This stage is critical in filling the porosity [36]. Finally, this process offers the unique possibility of modifying the structure and composition, and thereby the properties of ceramics, by designing the chemistry of the polymer precursor [61].…”

Section: Sic Fabrication Using Polymer Infiltration and Pyrolysismentioning

confidence: 99%

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

Zhang¹,

Singh²

2008

View full text Add to dashboard Cite

Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys based on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiC f -SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor components is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.Silicon carbide (SiC) is an important ceramic, most commonly used because of its excellent properties such as high strength, high modulus, excellent creep resistance and its high temperature stability. Moreover, crystalline silicon carbide is attracting wide attention as a promising candidate for several applications in nuclear reactors owing to its high thermal conductivity, high melting temperature, good chemical stability, and resistance to swelling under heavy ion bombardment. There have been many efforts to develop SiC based composites in various forms for use in advanced energy systems. However, fabricating SiC based composites by traditional powder processing route generally requires very high temperatures for pressureless sintering. In recent years, with the development of high yield preceramic precursors, the polymer infiltration and pyrolysis (PIP) method has aroused interest for the fabrication of ceramic based materials. Polymer derived ceramic materials offer unique advantages such as ability to fabricate net shaped components, incorporate reinforcements, along with lower processing temperatures, and perhaps most importantly relatively easy control over the microstructure. The raw materials are element-organic polymers whose composition and architecture can be tailored and varied.The primary focus of this work is to use a pyrolysis-based process to fabricate a host of novel silicon carbide-metal carbide/oxide composites, and to synthesize new materials based on mixed-metal (metal/silicon) carbides that cannot be processed using conventional techniques. These mixedcarbide material systems are expected to offer improved material properties for higher-temperature applications. Our fabrication technique resulted in both amorphous and nano-grained SiC matrix composites by controlled pyrolysis of allylhydridopolycarbosilane (AHPCS), the precursor for SiC for our study, under inert argon atmosphere.Cylindrical pellets, φ25 × 25 mm, were fabricated for bulk scale characterization. These samples were analyzed in terms of density and porosity, thermal conductivity, and flexural strength under multiaxial loading conditions. The final composition in the fabricated composite was studied use Xray diffraction (XRD). This was useful in understanding the relative stabil...

show abstract

“…However, in accident scenarios, Zr alloys react with hot The as-fabricated thermal conductivity of UO 2 -BeO fuel is calculated from the Hasselman and Johnson model, as shown below [10]. Considering the fabrication process of UO 2 -BeO fuel, introduced by Ishimoto et al [2] and Solomon et al [11], UO 2 is treated as a particle corresponding to subscript p in the Hasselman and Johnson model, and BeO is treated as a matrix, which corresponds to subscript m in the Hasselman and Johnson model. (6) k(UO 2 − BeO)-Thermal conductivity of the composite; V p -Volume fraction of particles; a-Radius of particle; h c -Interfacial thermal conductance.…”

Section: Introductionmentioning

confidence: 99%

Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings

Zhou

2018

Metals

View full text Add to dashboard Cite

Abstract:The thermophysical performance and solid mechanics behavior of UO 2 -36.4vol % BeO fuel pellets cladded with Zircaloy, SiC, and FeCrAl, and Zircaloy cladding materials coated with SiC and FeCrAl, are investigated based on simulation results obtained by the CAMPUS code. In addition, the effect of coating thickness (0.5, 1 and 1.5 mm) on fuel performance and mechanical interaction is discussed. The modeling results show that Zircaloy claddings are more effective in decreasing fuel centerline temperature and fission gas release than other kinds of cladding material because of the smaller gap between cladding and fuel at the same burnup. SiC claddings and SiC-coated Zircaloy claddings possess smaller plenum pressure than other kinds of cladding. SiC claddings contribute more to fuel radial displacement but less to fuel axial displacement. FeCrAl claddings exhibit very different radial and axial displacements in different axial positions. FeCrAl-coated Zircaloy claddings have a lower fuel centerline temperature than Zircaloy claddings at burnup below 850 MWh/kg U, but a higher fuel centerline temperature at higher burnup. The gap between FeCrAl-coated Zircaloy claddings and fuel pellets closes earlier than that of Zircaloy claddings. SiC-coated claddings increase fuel radial and axial displacements, and cladding axial displacements of inner and outer cladding surfaces.

show abstract

Enhanced Thermal Conductivity Oxide Fuels

Cited by 9 publications

References 1 publication

Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings

Contact Info

Product

Resources

About