Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors

Ikusawa, Yoshihisa; Maeda, Koji; Kato, Masato; Uno, Masayoshi

doi:10.1080/00295450.2017.1314748

“…Since the major composition of JOG is Cs2MoO4, the thermal conductivity of JOG is established by that of Cs2MoO4 as in the following equation valid for the given porosity range [Ikusawa 2017][Ishii 1997]: shows that the JOG with relatively small porosity is expected to have filled the fuel-cladding gap during irradiation. Eq.…”

Section: Thermal Hydraulics Discussionmentioning

confidence: 99%

Demonstration of NEAMS Multiphysics Tools for Fast Reactor Applications

Shemon

¹

,

Yu

²

,

Kim

³

2020

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The SHARP toolkit is a high-fidelity reactor simulation tool developed under the U.S. Department of Energy, Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. SHARP toolkit is comprised of the neutronics module PROTEUS thermal hydraulics module Nek5000, and structural mechanics module Diablo. During FY17 and FY18, the PROTEUS and Nek5000 components of SHARP were applied to solve challenging sodium-cooled fast reactor (SFR) problems. In particular, selected hot channel factors (HCF) for a prototype metal-fueled SFR design (the AFR-100) were analyzed in high fidelity, and the "SHARP zooming capability" for SFRs was developed and demonstrated to reduce computational expense for full core problems in cases where detailed data is needed in selected fuel assemblies.

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“…In order to investigate the thermal conductance of the gap, two literature correlations are referenced. Since the major composition of JOG is Cs2MoO4, one reference [Ikusawa 2017] assumes that the thermal conductivity of JOG is established by that of Cs2MoO4 as in the following equation:…”

Section: Thermal Hydraulics Discussionmentioning

confidence: 99%

“…Most of the annular pellets irradiated up to high burnup showed central-hole shrinkage due to deformation and restructuring during irradiation. This shrinkage has a great influence on power-to-melt, which is a main factor in deciding the maximum power in the fuel design [Ikusawa, 2017].…”

Section: Westinghouse Lead-cooled Fast Reactor Designmentioning

confidence: 99%

Extension and Demonstration of NEAMS Multiphysics Tools to Lead-Cooled, Sodium-Cooled, and Molten Salt Fast Reactor Applications

Shemon

¹

,

Yu

²

,

Jung

³

et al. 2019

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The SHARP toolkit is a high-fidelity reactor simulation tool developed under the U.S. Department of Energy, Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. SHARP toolkit is comprised of the neutronics module PROTEUS thermal hydraulics module Nek5000, and structural mechanics module Diablo. During FY17 and FY18, the PROTEUS and Nek5000 components of SHARP were applied to solve challenging sodium-cooled fast reactor (SFR) problems. In particular, selected hot channel factors (HCF) for a prototype metal-fueled SFR design (the AFR-100) were analyzed in high fidelity, and the "SHARP zooming capability" for SFRs was developed and demonstrated to reduce computational expense for full core problems in cases where detailed data is needed in selected fuel assemblies.

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“…Most of the annular pellets irradiated up to high burnup showed central-hole shrinkage due to deformation and restructuring during irradiation. This shrinkage has a great influence on power-to-melt, which is a main factor in deciding the maximum power in the fuel design [15]. The MOX (UPuO) fuel composition in the inner fuel zone is specified as a mixture of depleted uranium (0.25 wt% U-235) and enriched plutonium (68.769 wt% Pu-239, 1.759 wt% Pu-241), with 23% PuOx / (PuOx + UOx).…”

Section: Lfr Fuel Assembly Geometrymentioning

confidence: 99%

Assessment of Fast Reactor Hot Channel Factor Calculation Capability in Griffin and NekRS

Shemon¹,

Yu²,

Park³

et al. 2021

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The Laboratory's main facility is outside Chicago, at 9700 South Cass Avenue, Argonne, Illinois 60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov. DOCUMENT AVAILABILITYOnline Access: U.S. Department of Energy (DOE) reports produced after 1991 and a growing number of pre-1991 documents are available free at OSTI.GOV (http://www.osti.gov/), a service of the US Dept. of Energy's Office of Scientific and Technical Information.

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Oxide-Metal Ratio Dependence of Central Void Formation of Mixed Oxide Fuel Irradiated in Fast Reactors

Cited by 9 publications

References 15 publications

Demonstration of NEAMS Multiphysics Tools for Fast Reactor Applications

Demonstration of NEAMS Multiphysics Tools for Fast Reactor Applications

Extension and Demonstration of NEAMS Multiphysics Tools to Lead-Cooled, Sodium-Cooled, and Molten Salt Fast Reactor Applications

Assessment of Fast Reactor Hot Channel Factor Calculation Capability in Griffin and NekRS

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