Microstructure of 50 year old SCK•CEN BR1 research reactor fuel

Ann Leenaers; Sven Van den Berghe

Microstructure of 50 year old SCK•CEN BR1 research reactor fuel

Research output › peer-review

Abstract

The BR1 research reactor at SCK•CEN, Mol (Belgium) has a graphite core matrix loaded with fuel rods consisting of a natural uranium slug in an aluminum cladding. Fabrication reports show the application of a so-called AlSi bonding layer and an U(Al,Si)3 anti-diffusion layer on the natural uranium fuel slug to limit the interaction between the uranium fuel and aluminum cladding. The BR1 reactor is in operation since 1956 and still contains its original fuel rods. After more than 50 years irradiation at low temperature, the integrity of some of the fuel rods is investigated. The microstructure of the fuel, bonding and anti-diffusion layer and cladding is analysed using optical microscopy (OM), scanning electron microscopy (SEM) and electron microprobe analysis (EPMA).

Original language	English
Title of host publication	The RERTR-2007 International Meeting on reduced enrichment for research and test reactors
Place of Publication	Argonne, Illinois, United States
State	Published - 23 Sep 2007
Event	The RERTR-2007 International meeting on reduced enrichment for research and test reactors - Prague Duration: 23 Sep 2007 → 27 Sep 2007

Conference

Conference	The RERTR-2007 International meeting on reduced enrichment for research and test reactors
Country/Territory	Czech Republic
City	Prague
Period	2007-09-23 → 2007-09-27

Cite this

@inproceedings{f200f9a0ca334379839fdb08c50f3134,

title = "Microstructure of 50 year old SCK•CEN BR1 research reactor fuel",

abstract = "The BR1 research reactor at SCK•CEN, Mol (Belgium) has a graphite core matrix loaded with fuel rods consisting of a natural uranium slug in an aluminum cladding. Fabrication reports show the application of a so-called AlSi bonding layer and an U(Al,Si)3 anti-diffusion layer on the natural uranium fuel slug to limit the interaction between the uranium fuel and aluminum cladding. The BR1 reactor is in operation since 1956 and still contains its original fuel rods. After more than 50 years irradiation at low temperature, the integrity of some of the fuel rods is investigated. The microstructure of the fuel, bonding and anti-diffusion layer and cladding is analysed using optical microscopy (OM), scanning electron microscopy (SEM) and electron microprobe analysis (EPMA).",

keywords = "Research reactor fuel natural uranium BR1",

author = "Ann Leenaers and {Van den Berghe}, Sven",

note = "Score = 1; The RERTR-2007 International meeting on reduced enrichment for research and test reactors ; Conference date: 23-09-2007 Through 27-09-2007",

year = "2007",

month = sep,

day = "23",

language = "English",

booktitle = "The RERTR-2007 International Meeting on reduced enrichment for research and test reactors",

}

TY - GEN

T1 - Microstructure of 50 year old SCK•CEN BR1 research reactor fuel

AU - Leenaers, Ann

AU - Van den Berghe, Sven

N1 - Score = 1

PY - 2007/9/23

Y1 - 2007/9/23

N2 - The BR1 research reactor at SCK•CEN, Mol (Belgium) has a graphite core matrix loaded with fuel rods consisting of a natural uranium slug in an aluminum cladding. Fabrication reports show the application of a so-called AlSi bonding layer and an U(Al,Si)3 anti-diffusion layer on the natural uranium fuel slug to limit the interaction between the uranium fuel and aluminum cladding. The BR1 reactor is in operation since 1956 and still contains its original fuel rods. After more than 50 years irradiation at low temperature, the integrity of some of the fuel rods is investigated. The microstructure of the fuel, bonding and anti-diffusion layer and cladding is analysed using optical microscopy (OM), scanning electron microscopy (SEM) and electron microprobe analysis (EPMA).

AB - The BR1 research reactor at SCK•CEN, Mol (Belgium) has a graphite core matrix loaded with fuel rods consisting of a natural uranium slug in an aluminum cladding. Fabrication reports show the application of a so-called AlSi bonding layer and an U(Al,Si)3 anti-diffusion layer on the natural uranium fuel slug to limit the interaction between the uranium fuel and aluminum cladding. The BR1 reactor is in operation since 1956 and still contains its original fuel rods. After more than 50 years irradiation at low temperature, the integrity of some of the fuel rods is investigated. The microstructure of the fuel, bonding and anti-diffusion layer and cladding is analysed using optical microscopy (OM), scanning electron microscopy (SEM) and electron microprobe analysis (EPMA).

KW - Research reactor fuel natural uranium BR1

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_85247

UR - http://knowledgecentre.sckcen.be/so2/bibref/4700

M3 - In-proceedings paper

BT - The RERTR-2007 International Meeting on reduced enrichment for research and test reactors

CY - Argonne, Illinois, United States

T2 - The RERTR-2007 International meeting on reduced enrichment for research and test reactors

Y2 - 23 September 2007 through 27 September 2007

ER -