Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up

Ann Leenaers; Sven Van den Berghe; Francois Charollais; Patrick Lemoine; Christophe Jarousse; Anton Rohrmoser; Winfried Petry

Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up

Ann Leenaers, Sven Van den Berghe, Francois Charollais, Patrick Lemoine, Christophe Jarousse, Anton Rohrmoser, Winfried Petry

Research output › peer-review

Abstract

In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 w%), have been irradiated in the OSIRIS reactor. After unloading, the highest burn-up fuel plates, irradiated to local maximum burn-up of 66.5 and 88.3 % 235U LEU-equivalent, showed a local maximum thickness increase of respectively 178 and 323 m, but were still intact. Microstructural analyses (optical and scanning electron microscopy) on samples from these plates were performed at the hot laboratory (LHMA) of SCK•CEN in Mol, Belgium and provides information on the behavior of ground U(Mo) fuel irradiated to high burn-up.

Original language	English
Title of host publication	RERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors
Place of Publication	Argonne, IL, United States
State	Published - Nov 2009
Event	31st International Meeting on Reduced Enrichment for Research and Test Reactors - Beijing Duration: 1 Nov 2009 → 5 Nov 2009

Conference

Conference	31st International Meeting on Reduced Enrichment for Research and Test Reactors
Country/Territory	China
City	Beijing
Period	2009-11-01 → 2009-11-05

Cite this

@inproceedings{45d1daa6194b4df58fa40b71d5af4aa9,

title = "Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up",

abstract = "In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 w%), have been irradiated in the OSIRIS reactor. After unloading, the highest burn-up fuel plates, irradiated to local maximum burn-up of 66.5 and 88.3 % 235U LEU-equivalent, showed a local maximum thickness increase of respectively 178 and 323 m, but were still intact. Microstructural analyses (optical and scanning electron microscopy) on samples from these plates were performed at the hot laboratory (LHMA) of SCK•CEN in Mol, Belgium and provides information on the behavior of ground U(Mo) fuel irradiated to high burn-up.",

keywords = "MTR fuel, ground UMo",

author = "Ann Leenaers and {Van den Berghe}, Sven and Francois Charollais and Patrick Lemoine and Christophe Jarousse and Anton Rohrmoser and Winfried Petry",

note = "Score = 3; 31st International Meeting on Reduced Enrichment for Research and Test Reactors ; Conference date: 01-11-2009 Through 05-11-2009",

year = "2009",

month = nov,

language = "English",

booktitle = "RERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors",

}

Leenaers, A , Van den Berghe, S, Charollais, F, Lemoine, P, Jarousse, C, Rohrmoser, A & Petry, W 2009, Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up. in RERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors. Argonne, IL, United States, 31st International Meeting on Reduced Enrichment for Research and Test Reactors, Beijing, China, 2009-11-01.

TY - GEN

T1 - Microstructural analysis of ground U(Mo) fuel with and without Si in the matrix, irradiated to high burn-up

AU - Leenaers, Ann

AU - Van den Berghe, Sven

AU - Charollais, Francois

AU - Lemoine, Patrick

AU - Jarousse, Christophe

AU - Rohrmoser, Anton

AU - Petry, Winfried

N1 - Score = 3

PY - 2009/11

Y1 - 2009/11

N2 - In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 w%), have been irradiated in the OSIRIS reactor. After unloading, the highest burn-up fuel plates, irradiated to local maximum burn-up of 66.5 and 88.3 % 235U LEU-equivalent, showed a local maximum thickness increase of respectively 178 and 323 m, but were still intact. Microstructural analyses (optical and scanning electron microscopy) on samples from these plates were performed at the hot laboratory (LHMA) of SCK•CEN in Mol, Belgium and provides information on the behavior of ground U(Mo) fuel irradiated to high burn-up.

AB - In the framework of the IRIS-TUM irradiation program, several full size, flat dispersion fuel plates containing ground U(Mo) fuel kernels in an aluminum matrix, with and without addition of silicon (2.1 w%), have been irradiated in the OSIRIS reactor. After unloading, the highest burn-up fuel plates, irradiated to local maximum burn-up of 66.5 and 88.3 % 235U LEU-equivalent, showed a local maximum thickness increase of respectively 178 and 323 m, but were still intact. Microstructural analyses (optical and scanning electron microscopy) on samples from these plates were performed at the hot laboratory (LHMA) of SCK•CEN in Mol, Belgium and provides information on the behavior of ground U(Mo) fuel irradiated to high burn-up.

KW - MTR fuel

KW - ground UMo

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_101538

UR - http://knowledgecentre.sckcen.be/so2/bibref/6295

M3 - In-proceedings paper

BT - RERTR 2009 - 31th International Meeting on Reduced Enrichment for Research and Test Reactors

CY - Argonne, IL, United States

T2 - 31st International Meeting on Reduced Enrichment for Research and Test Reactors

Y2 - 1 November 2009 through 5 November 2009

ER -