Distributions of radionuclides on and in spent nuclear fuel claddings of pressurized water reactors

Hirabayashi, Toshiyuki; Sato, Tetsuya K.; Sagawa, Chiaki; Masaki, Nobuo; Saeki, Masakatsu; Adachi, T.

doi:10.1016/0022-3115(90)90419-n

Cited by 27 publications

(19 citation statements)

References 2 publications

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“…For the case of a mean fuel rod of a PWR running on a standard 4 cycles fuel management to a burn-up of 43 GW d t À1 , a maximum release of 40 GBq was obtained, corresponding to a total fractional release of 60%. This computation is consistent with the partition of tritium between the Zry4 cladding and the fuel measured in hot cells after irradiation [33,34].…”

Section: Power Reactor Conditionssupporting

confidence: 79%

Release of fission tritium through Zircaloy-4 fuel cladding tubes

Andrieu

Ravel

Ducros

et al. 2005

Journal of Nuclear Materials

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Section: Power Reactor Conditionssupporting

confidence: 79%

Release of fission tritium through Zircaloy-4 fuel cladding tubes

Andrieu

Ravel

Ducros

et al. 2005

Journal of Nuclear Materials

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“…The phase change of Zr02 identified in our examinations is attributed to fission damage. There are indications that fission products in the cladding, which were implanted by recoil, have been analyzed by a radiochemical technique (22) Therefore, monoclinic ZrOz film would be easily changed to the cubic phase even in low burnup fuels. The formation of a substitutional solid solution progresses during irradiation due to a strong contact between cubic UOz and ZrO2 at higher burnups, which induces subsequent mutual diffusion of U and Zr.…”

Section: Formation Process and Conditions Of Bondingmentioning

confidence: 99%

Formation of Pellet-Cladding Bonding Layer in High Burnup BWR Fuels.

Nogita¹,

Une²

1997

J. Nucl. Sci. Technol.

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Formation process of the pellet-cladding bonding layer was studied by EPMA, XRD, and SEM/TEP\/I for the oxide layer on a cladding inner surface and the bonding layer in irradiated fuel rods. Specimens were prepared from fuels which had been irradiated t o the pellet average burnups of 15, 27 and 42GWd/t in BWRs. In the lower burnup specimens of 15 and 27GWd/t, no bonding layer was found, while the higher burnup specimens of 42 and previously reported 49GWd/t had a typical bonding layer. A bonding layer which consisted of two regions was found in the latter fuels. One region of the inner surface of the cladding was made up mainly of ZrOz. The structure of this ZrOz consisted of cubic phase, while no monoclinic crystals were found. The other region, near the pellet surface, had both a cubic solid solution of (U, Zr)Oz and amorphous phase. Even in the lower burnup specimens having no bonding layer, cubic ZrOz phase was identified in the cladding inner oxide layer. The formation process of the bonding layer were discussed in connection with phase transformation by irradiation damage of fission products and conditions for contact of pellet and cladding. K E Y W O R D S: uranium dioxide, fuel pellets, cladding, zirconium oxides, bonding layer, burnup, B W R type reactors, scanning electron microscopy, electron probe microanalyzer, X-ray diffractometry, transmission electron microscopy, cubic phase, monoclinic phase, amorphous state, solid solutions, phase transformations, radiation damage, phase studies

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“…Zircaloy-4 bonded with stainless steel (304, 304L, 316 and 316L) is being used extensively in various technological applications concerning especially the pressure tubes and fuel elements in some nuclear power plants [1][2][3]. Joining of these two materials by fusion welding is undesirable because brittle intermetallic compounds such as ZrFe 2 , ZrFe 3 and Zr(Cr,Fe) 2 are formed in the welded zone [4] which reduce the mechanical strength as well as the corrosion resistance at the weld joints [5].…”

Section: Introductionmentioning

confidence: 99%