Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature

Allen, Todd R.; Kaoumi, Djamel; Wharry, Janelle P.; Jiao, Zhijie; Topbasi, Cem; Kohnert, Aaron A.; Barnard, Leland; Certain, Alicia G.; Field, Kevin G.; Was, Gary S.; Morgan, Dane; Motta, Arthur T.; Wirth, Brian D.; Yang, Ying

doi:10.1557/jmr.2015.99

Cited by 37 publications

(22 citation statements)

References 102 publications

(155 reference statements)

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“…As dose increases, loops exhibit only marginal growth, suggesting the size of loops are largely stable up to higher doses. This result is consistent with loop growth observations in various ferritic-martensitic alloys [16,23,138] and austenitic stainless steels [42], and it supports the theory of defect cluster saturation developed by Whapham and Makin [136,137]. It is also reasonably consistent with a study by He et al [9] on the same ODS alloy, where dislocation loops averaged 15.4 nm after proton irradiation to 3.7 dpa at 400°C.…”

Section: Dislocation Loopssupporting

confidence: 92%

“…This model has also been corroborated by experimental observation, in which dislocation loop morphology appears to approach a saturation point at higher dose [16,23,138]. …”

Section: Dislocation Loopssupporting

confidence: 68%

“…Another study by Allen, et al [16] observed a potential difference in the incubation period of G-phase nucleation, noting that clusters are observed between 1 and 3 dpa upon proton irradiation at 400°C, but are not present until ~7 dpa upon Fe 2+ irradiation at the same temperature. …”

Section: G-phase Clustersmentioning

confidence: 98%

“…Clusters are commonly observed alongside G-phases [16,[23][24][25], although their formation is typically attributed to the low solubility limits of Cu in b.c.c.…”

Section: Cu-rich Clustersmentioning

confidence: 99%

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The Mechanism of Radiation-Induced Nanocluster Evolution in Oxide Dispersion Strengthened and Ferritic-Martensitic Alloys

Swenson¹

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Section: Dislocation Loopssupporting

confidence: 92%

“…This model has also been corroborated by experimental observation, in which dislocation loop morphology appears to approach a saturation point at higher dose [16,23,138]. …”

Section: Dislocation Loopssupporting

confidence: 68%

Section: G-phase Clustersmentioning

confidence: 98%

“…Clusters are commonly observed alongside G-phases [16,[23][24][25], although their formation is typically attributed to the low solubility limits of Cu in b.c.c.…”

Section: Cu-rich Clustersmentioning

confidence: 99%

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The Mechanism of Radiation-Induced Nanocluster Evolution in Oxide Dispersion Strengthened and Ferritic-Martensitic Alloys

Swenson¹

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“…Improved structural materials that are capable of withstanding a higher radiation dose are under development, and irradiation experiments to higher fast neutron fluence are being pursued. 41 A sensitivity study is conducted to quantify the improvement of the S&B core performance in response to successful development and certification of structural materials that will enable increasing the radiation damage limit from 200 to 300 dpa or 400 dpa. For this sensitivity analysis, the dpa value of the seed fuel is still kept at 200 dpa since …”

Section: Vd Radiation Damage Constraint and Phased Development Of Bmentioning

confidence: 99%

Advanced Burner Reactors with Breed-and-Burn Thorium Blankets for Improved Economics and Resource Utilization

2017

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-This paper assesses the feasibility of designing seed-and-blanket (S&B) sodium-cooled fast reactor (SFR) cores to generate a significant fraction of the core power from radial thorium-fueled blankets that operate in the breed-and-burn (B&B) mode. The radiation damage on the cladding material in both seed and blanket does not exceed the presently acceptable constraint of 200 displacements per atom (dpa). The S&B core is designed to have an elongated seed (or driver) to maximize the fraction of neutrons that radially leak into the subcritical B&B blanket and reduce the neutron loss via axial leakage. A specific objective of this study is to maximize the fraction of core power generated by the B&B blanket that is proportional to the neutron leakage rate from the seed to the blanket. Since the blanket feed fuel is very inexpensive and requires no reprocessing and remote fuel fabrication, a larger fraction of power from the blanket will result in a lower fuel cycle cost per unit of electricity generated by the SFR core. It is found possible to design the seed of the S&B core to have a lower transuranics (TRU) conversion ratio (CR) than a conventional advanced burner reactor (ABR) core without deteriorating core safety. This is due to the unique synergism between a low CR seed and the B&B thorium blanket. The benefits of the synergism are maximized when using an annular seed surrounded by inner and outer thorium blankets. Two high-performance S&B cores are designed to benefit from the annular seed concept: (1) an ultra-long-cycle core having a CR = 0.5 seed and a cycle length of~7 effective full-power years (EFPYs) and (2) a high-transmutation core having a TRU CR of 0.0. The TRU transmutation rate of the latter core is comparable to that of the reference ABR with a CR of 0.5, and the thorium blanket can generate close to 60% of the core power. Because of the high blanket power fraction along with the high discharge burnup of the CR = 0 seed, the reprocessing capacity per unit of core power required by this S&B core is only approximately 1/6th that of the reference ABR core with a TRU CR of 0.5. Although the seed fuel CR is nearly zero, the burnup reactivity swing is low enough to enable a cycle length of more than 4 EFPYs. This is attributed to a combination of reactivity gain in the thorium blankets over the cycle and the relatively high heavy metal inventory. Moreover, despite the very low leakage, the S&B cores feature a less positive coolant reactivity coefficient and large enough negative Doppler coefficient even when using nonfertile fuel for the seed, because of the unique physics properties of the 233 U and Th in the thorium blankets. With the long cycles, the S&B SFR is expected to have a higher capacity factor, and therefore a lower cost of electricity, than conventional ABRs. The discharge burnup of the thorium blanket fuel is typically 70 MWd/kg such that the thorium fuel utilization is approximately 12 times that of natural uranium in light water reactors. A sensitivity study is subsequently un...

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Rate Theory Model of Irradiation-Induced Solute Clustering in b.c.c. Fe-Based Alloys

Swenson

Wharry

2020

JOM

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Solute nanoclusters are critical to the structural and mechanical integrity of numerous alloys based on the b.c.c. Fe matrix, which have risen to prominence as candidates for advanced nuclear reactor applications. Because irradiation can profoundly alter the morphology and composition of these solute nanoclusters, it is critical to understand and predict solute clustering behavior in the presence of irradiation. In this study, we advance a simple theory to model irradiation-induced nanocluster evolution subject to different irradiating particles. The model is trained and validated with experimental data following an approach similar to training a machine learning algorithm, resulting in an agile model that can be used for rapid screening of new alloys. Using the model, nanocluster evolution is found to depend upon the disordering parameter (i.e., cluster morphology and dose rate) and irradiation temperature, and is most sensitive to the solute migration, vacancy formation, and vacancy migration energies. Results are discussed with respect to the irradiation temperature shift for varying irradiating particle types and dose rates.

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Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature

Abstract: Abstract

Cited by 37 publications

References 102 publications

The Mechanism of Radiation-Induced Nanocluster Evolution in Oxide Dispersion Strengthened and Ferritic-Martensitic Alloys

The Mechanism of Radiation-Induced Nanocluster Evolution in Oxide Dispersion Strengthened and Ferritic-Martensitic Alloys

Advanced Burner Reactors with Breed-and-Burn Thorium Blankets for Improved Economics and Resource Utilization

Rate Theory Model of Irradiation-Induced Solute Clustering in b.c.c. Fe-Based Alloys

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