Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures

Cohen, Adam B.; Tsai, H.; Neimark, L.A.

doi:10.1016/0022-3115(93)90223-l

Cited by 72 publications

(46 citation statements)

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“…Line 1 agrees with the developed and tested at ANL fuel pins with "metallurgical" method of FCCI decrease (fuel column-U-19% Pu-10% Zr, cladding-ferriticmartensitic steel HT-9, Na-filling) (Cohen et al, 1993).…”

Section: Fcci Effects (Metal Fuel-steel Cladding)supporting

confidence: 77%

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Radiation and Thermal Effects in Experimental High Dense Metal Fuel Elements for Advanced LMFR

Yulian¹

2013

Energy Research Journal

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Known disadvantages of high-dense α-U metal fuel (intense radiation growth and radiation swelling, poor compatibility with steel claddings) can be reduced to the minimum by "constructive" approaches based on mechanical restraint of radiation growth and swelling and also on application of protective layers on fuel columns and claddings. Effectiveness of these methods has been confirmed during irradiation of full-sized fuel pins with high-dense metal fuel (γ eff ≥12.5g h.a./cm 3 ) in the BOR-60 and BN-350 reactors.

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Section: Fcci Effects (Metal Fuel-steel Cladding)supporting

confidence: 77%

“…It is reported (Cohen et al, 1993), that in EBR-II fuel pins irradiated up to the burnup 5-10%h.a., depth of corrosion damage for HT-9 claddings, being in close contact with the fuel column (U-19Pu-10 Zr wt.%), was as high as 33-57 µm at cladding temperatures about 550°С.…”

Section: Fcci Effects (Metal Fuel-steel Cladding)mentioning

confidence: 99%

Radiation and Thermal Effects in Experimental High Dense Metal Fuel Elements for Advanced LMFR

Yulian¹

2013

Energy Research Journal

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“…[6][7][8][9]13] Figure 3 shows isothermal sections for three ternary subsystems at 973 K (700°C). Different phases can form in Fe-U-Pu subsystem, such as FeU 6 , Fe 2 U, Fe 2 Pu, b-U, g, a-Fe, and bcc phase, also known as (U, Pu)ht.…”

Section: Resultsmentioning

confidence: 99%

“…Out-of-pile annealing tests on diffusion couples have been conducted to investigate FCCI behavior between U-Zr and U-Pu-Zr fuel alloys and Fe, Fe-12Cr, and HT-9 cladding. [4][5][6][7][8][9][10][11] The most inclusive study of quaternary U-Pu-Zr-Fe system at 973 K (700°C) has been conducted using thermal analysis and energy-dispersive spectroscopy (EDS) in scanning electron microscope (SEM). [9] However, there are issues associated with the characterization of Pu phases using EDS such as unavailability of U and Pu standards for appropriate EDS calibration, spatial resolution, magnification-dependent sensitivity of the technique, and overlaps of U and Pu EDS peaks, all of which restrict accurate quantitative chemical analysis of Pu-based phases in SEM.…”

Section: Introductionmentioning

confidence: 99%

Fuel-Cladding Interaction Between U-Pu-Zr Fuel and Fe

Aitkaliyeva

Madden

Miller

et al. 2015

Metallurgical and Materials Transactions E

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This work investigates fuel-cladding chemical interaction (FCCI) between U-25Pu-14Zr (in wt pct) fuel and pure Fe at elevated temperatures, understanding of which is critical for evaluation of the fuel performance. Phases and microstructure formed in the quaternary uranium-plutonium-zirconium-iron (U-Pu-Zr-Fe) system were characterized using the transmission electron microscopy technique. Phases formed within the FCCI layer were identified using selective area electron diffraction (SAED) analysis as Fe 2 U (Fd-m), Fe 2 Zr (Fd-3m), a-U (Cmcm), Fe 2 Pu (Fd-3m), b-Pu (C12/m1), and b-Zr (Im-3m).

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“…The U and Pu constituents in the fuel, however, tend to interact metallurgically with iron-based claddings at elevated temperatures during nominal steady-state operating conditions and off-normal reactor events. In particular, if the temperature is raised above the eutectic temperature of the metallic fuel, e.g., during an off-normal reactor event, the fuel can form a mixture of liquid and solid phases that may promote a further cladding interaction [2,3]. In addition, lanthanide fission products such as Nd, Ce, La, Pr and Sm migrate into the fuel slug-cladding interface during irradiation and lower the eutectic threshold temperature, so that, eventually, they promote the eutectic reaction between the fuel slug and cladding.…”

Section: Introductionmentioning

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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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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Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures

Cited by 72 publications

References 0 publications

Radiation and Thermal Effects in Experimental High Dense Metal Fuel Elements for Advanced LMFR

Radiation and Thermal Effects in Experimental High Dense Metal Fuel Elements for Advanced LMFR

Fuel-Cladding Interaction Between U-Pu-Zr Fuel and Fe

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

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