Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends

Hall, B. R.; Sweet, Ryan; Belles, Randy; Wieselquist, William

doi:10.2172/1783010

Cited by 6 publications

(9 citation statements)

References 20 publications

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“…The enrichment and end-ofequilibrium cycle discharge burnup are used as inputs to a single assembly SCALE calculation that is used to derive the end-of-cycle inventory. With Cr cladding, the penalty to enrichment is small (of the order of 0.1%) [6]. The same inventory and discharge burnup is, therefore, used for the Cr-coated case as for the reference Zr case.…”

Section: Reactor Designmentioning

confidence: 99%

Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup [Slides]

Allaf,

Whitmeyer,

Duarte

et al. 2024

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Section: Reactor Designmentioning

confidence: 99%

Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup [Slides]

Allaf,

Whitmeyer,

Duarte

et al. 2024

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“…Many of these fabricators are working jointly with government-owned laboratories within their nations. In 2022, a more comprehensive ORNL/TM report (Hall et al 2021) on ATF R&D was discovered and supplements the less detailed fabricator information below:…”

Section: D1-11212 Potential Atf Fuel Fabricatorsmentioning

confidence: 99%

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Williams,

Hansen,

Hoffman

2023

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“…In the design specifications shown in Table 2, the ATF pins include a small amount of metal oxide dopant (Al 2 O 2 and Cr 2 O 3 ) within the UO 2 fuel. Advantages of this dopant include greater densification and grain size during fuel sintering, leading to lower fuel densification during irradiation [8]. The net result of these effects may include higher achievable fuel burnups and a lower probability of pellet-clad interaction and, ultimately, a lower likelihood of fuel failure [8].…”

Section: Polaris Pwr Assembly Modelmentioning

confidence: 99%

“…The main goal of additional fuel enrichment in LEU+ fuel designs (5.0 − 10.0 w /o 235 U) is to improve fuel economy in the current reactor fleet, enabling higher burnup than that of typical reactor fuels [6], [7]. ATF designs are used to improve the safety level of the fuel system under accident conditions [8].…”

Section: Introductionmentioning

confidence: 99%

Transition Core Modeling for Extended Enrichment & Accident-Tolerant Fuels Using Polaris/PARCS

Skutnik¹,

Mertyurek²,

Oktavian

et al. 2023

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Commercial light water reactor (LWR) operators and fuel vendors are currently interested in increasing the low-enriched uranium (LEU) fuel enrichments from the current limit of 5.0 w /o 235 U up to 10 w /o 235 U (referred to as "LEU+") in their current fleets; they are also interested in using accident-tolerant fuel (ATF) with both LEU and LEU+ fuel. This report aims to identify modeling challenges and accuracy concerns in transition core analysis using the SCALE Polaris lattice physics code [1], [2] and U.S. Nuclear Regulatory Commission core simulator PARCS [3].At the time this study was started, no publicly available LEU+ core designs existed for boiling water reactor (BWR) or pressurized water reactor (PWR) systems. Therefore, fuel lattices were shuffled within a multi-assembly model to mimic neutronically challenging lattice combinations seen in transition cores, such as a fresh LEU+ lattice next to depleted LEU lattices. In addition to multi-assembly models, whole-core BWR transition core calculations were performed for ATF and LEU+ fuel using an existing Hatch-1 Cycle 3 core model [4]. A whole-core BWR model was chosen due to the more heterogeneous core designs compared to those for a PWR core. Since the original core is an old checkerboard core design and no core or fuel design optimization was performed for the modeled fuel types, these core calculations were intended only to provide:• Comparisons of core characteristics of interest, such as the pin power distributions and peaking factors, Doppler temperature coefficients (DTCs), and control blade worths (CBWs) under challenging core designs,• Identification of reactor physics challenges in modeling LEU+ and ATF cores,• A stress test for the Polaris/PARCS two-step modeling approach, including characterization of the relative accuracy for predicting characteristics of interest such as pin power distributions.As a secondary means of validating the Polaris/PARCS multi-assembly models, high-fidelity continuous energy (CE) Monte Carlo calculations were performed using Serpent [5] on equivalent lattice models. The pin-wise powers for the Polaris/PARCS and Serpent models were compared with the Polaris lattice model to establish the consistency of the pin power distribution across the different multi-assembly models. Finally, the effect of using additional coarse-energy groups (four and eight groups) was investigated with PARCS to determine what (if any) gains in accuracy could be realized when compared to Polaris.The fuel lattices used for this study are based upon previously designed fuel lattices in Phase 1 studies [6],[7], with minor modifications to the BWR design to achieve a practical cycle length and lower overall power peaking factor (PPF). These original assemblies include a standard Westinghouse 17×17 PWR fuel with 6.5 w /o 235 U and 8 w /o 235 U enrichment LEU+ lattice designs and GE-14 10×10 BWR fuel designs with 8.0 w /o 235 U maximum (7.0 w /o 235 U average) and 10.0 w /o 235 U maximum (8.7 w /o 235 U average) enrichment maps. On the other hand, P...

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Extended Enrichment Accident Tolerant LWR Fuel Isotopic and Lattice Parameter Trends

Cited by 6 publications

References 20 publications

Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup [Slides]

Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup [Slides]

Advanced Fuel Cycle Cost Basis Report: Module D1-1: Uranium-based Ceramic LWR Fuel Fabrication (Rev.2)

Transition Core Modeling for Extended Enrichment & Accident-Tolerant Fuels Using Polaris/PARCS

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