Short-term irradiation behavior of minor actinide doped uranium plutonium mixed oxide fuels irradiated in an experimental fast reactor

Maeda, Koji; Sasaki, Shinji; Kato, Masato; Kihara, Yoshiyuki

doi:10.1016/j.jnucmat.2008.12.041

Cited by 25 publications

(13 citation statements)

References 3 publications

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“…Physical property measurements, fuel pellet preparation tests, and irradiation tests of Np-and Am-bearing MOX (Np/Am-MOX) fuels have been carried out as a part of the development. [4][5][6][7][8][9][10][11][12][13][14][15][16][17] To develop such new fuels, it is essential to evaluate irradiation behavior. However, irradiation data is little in the early phase of development.…”

Section: Introductionmentioning

confidence: 99%

“…The first irradiation tests of Np/Am-MOX fuels were carried out in the experimental fast reactor Joyo as a function of O=M ratio. [4][5][6] The maximum linear heat rate of the fuel attained 432 W/cm and was held for 24 h. The microstructure and elemental distribution on the cross section of the pellets were analyzed in postirradiation examinations (PIEs), and the irradiation behavior was analyzed by using fitting parameters. This approach can be applied to irradiation behavior analysis only under limited condition.…”

Section: Introductionmentioning

confidence: 99%

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Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

Kato

Maeda

Ozawa

et al. 2011

Journal of Nuclear Science and Technology

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The physical properties and irradiation behavior of Np-and Am-bearing MOX were evaluated for the development of advanced fast reactor fuels. The physical properties, lattice parameter, melting temperature, thermal conductivity, and oxygen potential of the fuels were described as functions of Np content, Am content, and oxygen-to-metal (O=M) ratio, and the effect of a few percent Np and Am addition into MOX on those properties was found to be negligibly small. The irradiation tests of fuel pellets having O=M ratios of 1.98 or 1.96 were carried out at a high linear heat rate of about 430 W/cm for 24 h. The redistributions of actinide element and oxygen were analyzed by using the physical properties for Np-and Am-bearing MOX, and the maximum temperatures of the pellets were estimated. The maximum temperatures of the pellets of O=M ¼ 1:96 and 1.98 were estimated to be 2,701 and 2,510 K, respectively. The analysis result showed that the higher maximum temperature in the low-O=M pellet was caused by the low thermal conductivity in the outer region of the pellets, and the maximum temperatures of the pellets did not exceed their melting temperatures. In the results of postirradiation examination, no trace of melting was observed.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

Kato

Maeda

Ozawa

et al. 2011

Journal of Nuclear Science and Technology

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“…Figure 16 showed bubble number density. The area used to measure the bubble number density of each specimen was 0.186 μm 2 , and the number density per volume was determined by the three-halves power of the number density per unit area. In the figure, the theoretical lines were also plotted and their details are discussed in Section 4.…”

Section: Methodsmentioning

confidence: 99%

“…Minor actinide-containing (MA-containing) MOX fuels have been developed as one of the methods to accomplish a feasible fuel cycle by transmutation of long-lived MAs in fast breeder reactors [1,2]. However, because some of the MAs are α-decay emitters with a short half-life, more helium atoms are accumulated in the MA-MOX fuels than in UO 2 fuels.…”

Section: Introductionmentioning

confidence: 99%

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Dependence of vacancy concentration on morphology of helium bubbles in oxide ceramics

Matsunaga¹,

Sakamoto²,

Muta

et al. 2014

Journal of Nuclear Science and Technology

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Since the formation of helium bubbles degrades swelling property and thermal conductivity of minor actinide-containing mixed oxide (MA-MOX) fuel, it is essential to understand the conditions of the bubble formation. In order to examine the dependence of vacancy concentration on morphology of helium bubbles, helium was infused into (Zr,Fe)O 2−x . The oxygen vacancy concentration was controlled by addition of solute Fe 3 + into ZrO 2 . Helium was infused by hot isostatic pressing. The helium-infused specimens were observed by field emission scanning electron microscopy (FE-SEM) and field emission transmission electron microscopy (FE-TEM). In addition, X-ray fluorescence, X-ray diffraction analysis, conversion electron yield-X-ray absorption near-edge structure and FE-SEM/EDX (energy dispersive X-ray) analyses were also made to interpret the results of microstructure observations. As a result of the helium infusion treatment, numerous 0.5-10 nm bubbles were observed and its number density clearly depended on oxygen vacancy concentration. On the other hand, sizes of the helium nano-bubbles in all specimens were almost constant.

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Actinide-Bearing Fuels and Transmutation Targets

Pillon¹

2012

Comprehensive Nuclear Materials

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Short-term irradiation behavior of minor actinide doped uranium plutonium mixed oxide fuels irradiated in an experimental fast reactor

Cited by 25 publications

References 3 publications

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

Dependence of vacancy concentration on morphology of helium bubbles in oxide ceramics

Actinide-Bearing Fuels and Transmutation Targets

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