Effect of fission rate on the microstructure of coated UMo dispersion fuel

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Effect of fission rate on the microstructure of coated UMo dispersion fuel. / Leenaers, Ann; Parthoens, Yves; Cornelis, Guy; Kuzminov, Vadim; Van den Berghe, Sven; Koonen, Edgar; Ye, Bei; Hofmann, Gerard L.; Schulthess, Jason.

In: Journal of Nuclear Materials, Vol. 494, 494, 01.10.2017, p. 10-19.

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@article{b3eb62749538453bb7b637d1aa742dac,
title = "Effect of fission rate on the microstructure of coated UMo dispersion fuel",
abstract = "Compared to previous irradiation experiments containing UMo/Al dispersion fuel plates, the SELENIUM irradiation experiment performed at the SCK·CEN BR2 reactor in 2012 showed an improved plate swelling behavior. However, in the high burn-up area of the plates a significant increase in meat thickness was still measured. The origin of this increase is currently not firmly established, but it is clear from the observed microstructure that the swelling rate still is too high for practical purposes and needs to be reduced. It was stipulated that the swelling occurred at the high burnup areas which are also the high power zones at beginning of life. For that reason, an experiment was proposed to investigate the influence of fission rate (i.e. power) on some of the observed phenomena. For this purpose, a sibling plate to a high power (BOL>470 W/cm2) SELENIUM plate was irradiated during four BR2 cycles. The SELENIUM 1a fuel plate was submitted to a local maximum heat flux below 350 W/cm2, throughout the full irradiation. At the end of the last cycle, the SELENIUM 1a fuel plate reached a maximum local burnup value of close to 75{\%}235U compared to 70{\%}235U for the SELENIUM high power plates. When comparing to the results on the SELENIUM plates, the non-destructive tests clearly show a continued linear swelling behavior of the low power irradiated fuel plate SELENIUM 1a in the high burn-up region. The influence of the fission rate is also evidenced in the microstructural examination of the fuel showing that there is no formation of interaction layer at the high burn-up region.",
keywords = "UMo dispersion fuel, BR2",
author = "Ann Leenaers and Yves Parthoens and Guy Cornelis and Vadim Kuzminov and {Van den Berghe}, Sven and Edgar Koonen and Bei Ye and Hofmann, {Gerard L.} and Jason Schulthess",
note = "Score=10",
year = "2017",
month = "10",
day = "1",
doi = "10.1016/j.jnucmat.2017.06.036",
language = "English",
volume = "494",
pages = "10--19",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

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TY - JOUR

T1 - Effect of fission rate on the microstructure of coated UMo dispersion fuel

AU - Leenaers, Ann

AU - Parthoens, Yves

AU - Cornelis, Guy

AU - Kuzminov, Vadim

AU - Van den Berghe, Sven

AU - Koonen, Edgar

AU - Ye, Bei

AU - Hofmann, Gerard L.

AU - Schulthess, Jason

N1 - Score=10

PY - 2017/10/1

Y1 - 2017/10/1

N2 - Compared to previous irradiation experiments containing UMo/Al dispersion fuel plates, the SELENIUM irradiation experiment performed at the SCK·CEN BR2 reactor in 2012 showed an improved plate swelling behavior. However, in the high burn-up area of the plates a significant increase in meat thickness was still measured. The origin of this increase is currently not firmly established, but it is clear from the observed microstructure that the swelling rate still is too high for practical purposes and needs to be reduced. It was stipulated that the swelling occurred at the high burnup areas which are also the high power zones at beginning of life. For that reason, an experiment was proposed to investigate the influence of fission rate (i.e. power) on some of the observed phenomena. For this purpose, a sibling plate to a high power (BOL>470 W/cm2) SELENIUM plate was irradiated during four BR2 cycles. The SELENIUM 1a fuel plate was submitted to a local maximum heat flux below 350 W/cm2, throughout the full irradiation. At the end of the last cycle, the SELENIUM 1a fuel plate reached a maximum local burnup value of close to 75%235U compared to 70%235U for the SELENIUM high power plates. When comparing to the results on the SELENIUM plates, the non-destructive tests clearly show a continued linear swelling behavior of the low power irradiated fuel plate SELENIUM 1a in the high burn-up region. The influence of the fission rate is also evidenced in the microstructural examination of the fuel showing that there is no formation of interaction layer at the high burn-up region.

AB - Compared to previous irradiation experiments containing UMo/Al dispersion fuel plates, the SELENIUM irradiation experiment performed at the SCK·CEN BR2 reactor in 2012 showed an improved plate swelling behavior. However, in the high burn-up area of the plates a significant increase in meat thickness was still measured. The origin of this increase is currently not firmly established, but it is clear from the observed microstructure that the swelling rate still is too high for practical purposes and needs to be reduced. It was stipulated that the swelling occurred at the high burnup areas which are also the high power zones at beginning of life. For that reason, an experiment was proposed to investigate the influence of fission rate (i.e. power) on some of the observed phenomena. For this purpose, a sibling plate to a high power (BOL>470 W/cm2) SELENIUM plate was irradiated during four BR2 cycles. The SELENIUM 1a fuel plate was submitted to a local maximum heat flux below 350 W/cm2, throughout the full irradiation. At the end of the last cycle, the SELENIUM 1a fuel plate reached a maximum local burnup value of close to 75%235U compared to 70%235U for the SELENIUM high power plates. When comparing to the results on the SELENIUM plates, the non-destructive tests clearly show a continued linear swelling behavior of the low power irradiated fuel plate SELENIUM 1a in the high burn-up region. The influence of the fission rate is also evidenced in the microstructural examination of the fuel showing that there is no formation of interaction layer at the high burn-up region.

KW - UMo dispersion fuel

KW - BR2

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35786194

U2 - 10.1016/j.jnucmat.2017.06.036

DO - 10.1016/j.jnucmat.2017.06.036

M3 - Article

VL - 494

SP - 10

EP - 19

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

M1 - 494

ER -

ID: 5656094