Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

Bei Ye; S. Bhattacharya; K. Mo; D. Yun; M. Pellin; J. Fortner; Gerard Hofmann; A.M. Yacout; Tom Wiencek; Ann Leenaers; Sven Van den Berghe

doi:10.1016/j.jnucmat.2015.04.051

Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

Bei Ye, S. Bhattacharya, K. Mo, D. Yun, M. Pellin, J. Fortner, Gerard Hofmann, A.M. Yacout, Tom Wiencek, Ann Leenaers, Sven Van den Berghe

Research output › peer-review

Abstract

Irradiation responses of U–Mo/Al dispersion fuel have been investigated by irradiation with 84 MeV Xe26+ ions. Dispersion fuels fabricated with uncoated and ZrN-coated fuel particles were irradiated to various doses at 350 C. The highest dose achieved was 2.9 1017 ions/cm2 (1200 displacement per atom
(dpa)). Following the irradiation, scanning electron microscopy (SEM) and transmission electron microscopy (TEM) experiments were carried out to characterize the microstructures of the irradiated samples. The post irradiation examinations (PIE) revealed that: (1) crystalline interdiffusion product (UMo)Alx
developed at locations where no coating or compromised coating layer is present; (2) intact ZrN coating layers effectively blocked the interdiffusion between U–Mo and Al; (3) SEM-observable Xe bubbles distributed along grain/cell boundaries in U–Mo; and (4) gas bubble interlinkage was observed at a dose of 2.9 1017 ions/cm2.

Original language	English
Pages (from-to)	236-244
Number of pages	8
Journal	Journal of Nuclear Materials
Volume	464
DOIs	https://doi.org/10.1016/j.jnucmat.2015.04.051
State	Published - 6 May 2015

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10.1016/j.jnucmat.2015.04.051

Cite this

@article{7090e282691e4b9a9485320f746b6182,

title = "Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe",

abstract = "Irradiation responses of U–Mo/Al dispersion fuel have been investigated by irradiation with 84 MeV Xe26+ ions. Dispersion fuels fabricated with uncoated and ZrN-coated fuel particles were irradiated to various doses at 350 C. The highest dose achieved was 2.9 1017 ions/cm2 (1200 displacement per atom(dpa)). Following the irradiation, scanning electron microscopy (SEM) and transmission electron microscopy (TEM) experiments were carried out to characterize the microstructures of the irradiated samples. The post irradiation examinations (PIE) revealed that: (1) crystalline interdiffusion product (UMo)Alxdeveloped at locations where no coating or compromised coating layer is present; (2) intact ZrN coating layers effectively blocked the interdiffusion between U–Mo and Al; (3) SEM-observable Xe bubbles distributed along grain/cell boundaries in U–Mo; and (4) gas bubble interlinkage was observed at a dose of 2.9 1017 ions/cm2.",

keywords = "heavy ion irradiation, amorphisation, U-Mo/Al dispersion, fuel, irradiation, uncoated, ZrN-coated fuel particules, SEM, TEM, microstructures, PIE (Post-Irradiation Examination)",

author = "Bei Ye and S. Bhattacharya and K. Mo and D. Yun and M. Pellin and J. Fortner and Gerard Hofmann and A.M. Yacout and Tom Wiencek and Ann Leenaers and {Van den Berghe}, Sven",

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year = "2015",

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day = "6",

doi = "10.1016/j.jnucmat.2015.04.051",

language = "English",

volume = "464",

pages = "236--244",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

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T1 - Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

AU - Ye, Bei

AU - Bhattacharya, S.

AU - Mo, K.

AU - Yun, D.

AU - Pellin, M.

AU - Fortner, J.

AU - Hofmann, Gerard

AU - Yacout, A.M.

AU - Wiencek, Tom

AU - Leenaers, Ann

AU - Van den Berghe, Sven

N1 - Score=1

PY - 2015/5/6

Y1 - 2015/5/6

N2 - Irradiation responses of U–Mo/Al dispersion fuel have been investigated by irradiation with 84 MeV Xe26+ ions. Dispersion fuels fabricated with uncoated and ZrN-coated fuel particles were irradiated to various doses at 350 C. The highest dose achieved was 2.9 1017 ions/cm2 (1200 displacement per atom(dpa)). Following the irradiation, scanning electron microscopy (SEM) and transmission electron microscopy (TEM) experiments were carried out to characterize the microstructures of the irradiated samples. The post irradiation examinations (PIE) revealed that: (1) crystalline interdiffusion product (UMo)Alxdeveloped at locations where no coating or compromised coating layer is present; (2) intact ZrN coating layers effectively blocked the interdiffusion between U–Mo and Al; (3) SEM-observable Xe bubbles distributed along grain/cell boundaries in U–Mo; and (4) gas bubble interlinkage was observed at a dose of 2.9 1017 ions/cm2.

AB - Irradiation responses of U–Mo/Al dispersion fuel have been investigated by irradiation with 84 MeV Xe26+ ions. Dispersion fuels fabricated with uncoated and ZrN-coated fuel particles were irradiated to various doses at 350 C. The highest dose achieved was 2.9 1017 ions/cm2 (1200 displacement per atom(dpa)). Following the irradiation, scanning electron microscopy (SEM) and transmission electron microscopy (TEM) experiments were carried out to characterize the microstructures of the irradiated samples. The post irradiation examinations (PIE) revealed that: (1) crystalline interdiffusion product (UMo)Alxdeveloped at locations where no coating or compromised coating layer is present; (2) intact ZrN coating layers effectively blocked the interdiffusion between U–Mo and Al; (3) SEM-observable Xe bubbles distributed along grain/cell boundaries in U–Mo; and (4) gas bubble interlinkage was observed at a dose of 2.9 1017 ions/cm2.

KW - heavy ion irradiation

KW - amorphisation

KW - U-Mo/Al dispersion

KW - fuel

KW - irradiation

KW - uncoated

KW - ZrN-coated fuel particules

KW - SEM

KW - TEM

KW - microstructures

KW - PIE (Post-Irradiation Examination)

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/26697115

U2 - 10.1016/j.jnucmat.2015.04.051

DO - 10.1016/j.jnucmat.2015.04.051

M3 - Article

SN - 0022-3115

VL - 464

SP - 236

EP - 244

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -