Metal Fuel

Ogata, Takanari

doi:10.1016/b978-0-08-056033-5.00049-5

Cited by 25 publications

(35 citation statements)

References 61 publications

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Section: Results Of Irradiated Fuel After High-temperature Heating Testmentioning

confidence: 99%

“…Other phases are observed that primarily contain lanthanides [2,3,14,15]. Meanwhile, the Zr component in a fuel slug induces stable intermetallic compounds such as ZrFe2, which retards the further development of liquid-phase penetration [16,17]. In order to investigate the microstructure of the eutectic melting region in detail for the U-10Zr/T92 specimen, constituent distributions and the eutectic penetration depth were measured by utilizing SEM and EPMA (see Figure 12).…”

Section: Results Of Irradiated Fuel After High-temperature Heating Testmentioning

confidence: 99%

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Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Kim¹,

Cheon²,

Kim³

et al. 2016

Metals

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A microstructure observation using an optical microscope, SEM and EPMA was performed for the irradiated U-10Zr and U-10Zr-5Ce fuel slugs with a T92 cladding specimen after a high-temperature heating test. Also, the measured eutectic penetration rate was compared with the value predicted by the existing eutectic penetration correlation being used for design and modeling purposes. The heating temperature and duration time for the U-10Zr/T92 specimen were 750 • C and 1 h, and those for the U-10Zr-5Ce/T92 specimen were 800 • C and 1 h. In the case of the U-10Zr/T92 specimen, the migration phenomena of U, Zr, Fe, and Cr as well as the Nd lanthanide fission product were observed at the eutectic melting region. The measured penetration rate was similar to the value predicted by the existing eutectic penetration rate correlation. In addition, when comparing with measured eutectic penetration rates for the unirradiated U-10Zr fuel slug with FMS (ferritic martensitic steel, HT9 or Gr.91) cladding specimens which had been reported in the literature, the measured eutectic penetration rate for the irradiated fuel specimen was higher than that for the unirradiated U-10Zr specimen. In the case of the U-10Zr-5Ce/T92 specimen in which there had been a gap between the fuel slug and cladding after the irradiation test, the eutectic melting region was not found because contact between the fuel slug and cladding did not take place during the heating test.

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Section: Results Of Irradiated Fuel After High-temperature Heating Testmentioning

confidence: 99%

Section: Results Of Irradiated Fuel After High-temperature Heating Testmentioning

confidence: 99%

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Kim¹,

Cheon²,

Kim³

et al. 2016

Metals

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“…For vacancy clustering, the master equations are similar to Eqs. (17), (18), and (19), except that additional terms including the reactions of sinks and mutual recombination of point defects are needed to describe the evolution of vacancy monomers. The master equation for vacancy clustering can be expressed as…”

Section: Methodsmentioning

confidence: 99%

“…The bubbles and swelling affect physical properties of metallic fuels, such as the degradation of thermal conductivity and mechanical integrity. Such fission gas bubble forms at the central region of the metallic fuel where temperature is higher and the thermodynamically stable phase of bcc γ dominates [19].…”

Section: Introductionmentioning

confidence: 99%

Lower length scale informed improvements to Bison U-Pu-Zr fuel swelling model

Aagesen

Jokisaari

2020

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Due to renewed interest in metallic fuels from the U-(Pu)-Zr material system, significant improvements have recently been made to BISON's capability to simulate metallic fuel, particularly in the area of swelling. In this report, lower length scale simulations that have been conducted to inform the engineering-scale models in BISON during FY20 are described. For the high-temperature regions of the fuel that are dominated by the γ phase of U-(Pu)-Zr, two new models for swelling have implemented in BISON. Phase-field simulations were conducted to calculate parameters for these and other BISON models that control when gaseous swelling ceases and fission gas release begins. For the low-temperature regions of the fuel dominated by the α phase of uranium, microstructurally resolved simulations of pore growth and crystal deformation were performed to understand the effect of irradiation-generated crystal shape changes. Conformally meshed microstructures with pores were simulated with a crystal plasticity model and with a burnup eigenstrain model. Plastic deformation will not cause pore size to increase; burnup eigenstrain (irradiation-induced crystal shape changes) will increase the volume of existing porosity and cause it to become anisotropic in shape. Additional model development work for early-stage fission gas cluster/bubble formation in the γ phase were performed, by coupling with defect clustering within cluster dynamics framework. Sensitivity analysis were conducted to identify the critical thermo-kinetic parameters needed for rigorous assessment.

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“…The compositions of the FUTURIX-FTA pins and the AFC-1 rodlets were designed to investigate if minor actinides could be incorporated into the fuel of a fast reactor without significantly degrading fuel performance, as understood for previously well studied fuels. The general performance of metallic fuel in fast reactors has been well documented [15,16,17,18,19]. Likewise the irradiation performance of nitride fuels in fast reactors has also been documented, although the existing database for nitride fuels is much smaller than the database for metal fuels [20].…”

Section: Futurix-fta (Doe1234) Vs Afc-1mentioning

confidence: 99%

Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

Harp

Capriotti

Hayes

et al. 2017

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The testing of fast reactor fuels in the thermal-spectrum of the Advanced Test Reactor using cadmium-filtering has been underway since 2003. The objective of this experimental approach to create a temperature profile inside of test fuel rodlets that is nearly prototypic of corresponding fast reactor conditions. This requires, necessarily, that the power generation profile inside of test fuel rodlets also be nearly prototypic of corresponding fast reactor conditions. By doing so, this experimental approach should allow for the study of fast reactor fuel performance phenomena that are primarily dependent upon the conditions of temperature and/or temperature gradient inside the fuel to be possible using a thermal test reactor. Validation of this assertion has been undertaken by both supporting analyses and by comparing fuel performance phenomena observed in fuels irradiated in cadmium-filtered positions in ATR to similar or identical fuels irradiated under similar conditions in genuine fast reactors. This report documents a preliminary comparison of fuel performance data available from the testing of metallic, oxide, and nitride fuels in cadmium-filtered positions in the ATR to the performance of identical or similar fuels irradiated in genuine fast reactors. Although a variety of fuel performance metrics are presented, particular attention is paid to those phenomena that are primarily, or significantly, dependent on conditions of temperature and temperature gradient with the fuel. Although the comparisons presented in this report are at this time limited in scope and preliminary in nature, they do support the assertion that the objectives of the cadmium-filtered testing approach in ATR are both feasible and appear sound. The analyses and comparisons presented in this report show that ATR irradiations performed using cadmium shrouding are sufficiently prototypic Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report vi

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Metal Fuel

Cited by 25 publications

References 61 publications

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Results of High-Temperature Heating Test for Irradiated U-10Zr(-5Ce) with T92 Cladding Fuel

Lower length scale informed improvements to Bison U-Pu-Zr fuel swelling model

Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

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