Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS

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Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS. / Lemehov, Sergei; Sobolev, Vitaly; Govers, Kevin; Verwerft, Marc; Aït Abderrahim, Hamid.

International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators. Vienna, Austria, 2009.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Lemehov, S, Sobolev, V, Govers, K, Verwerft, M & Aït Abderrahim, H 2009, Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS. in International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators. Vienna, Austria, International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators, Vienna, Austria, 2009-05-04.

APA

Lemehov, S., Sobolev, V., Govers, K., Verwerft, M., & Aït Abderrahim, H. (2009). Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS. In International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators

Vancouver

Lemehov S, Sobolev V, Govers K, Verwerft M, Aït Abderrahim H. Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS. In International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators. Vienna, Austria. 2009

Author

Lemehov, Sergei ; Sobolev, Vitaly ; Govers, Kevin ; Verwerft, Marc ; Aït Abderrahim, Hamid. / Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS. International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators. Vienna, Austria, 2009.

Bibtex - Download

@inproceedings{e8ac4175c5b44068a96c9f857672dd7b,
title = "Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS",
abstract = "Transmutation of the minor actinides (neptunium, plutonium, americium and curium) in either a fast reactor (FR) or a fast accelerator-driven system (ADS) is currently considered as one of the promising options. The current reference fuels for a European ADS-transmuter are oxides such as MOX, (Cm,Am,Pu)O2 diluted in MgO, ZrO2, and Mo matrices. In the framework of the number of EC projects and its own project MYRRHA, the Belgian Nuclear Research Centre SCK•CEN started few years ago the studies on fuels for transmutation in ADS. To evaluate basic in-pile features of fuel design the full-scale fuel performance code MACROS has been developed and is currently used. This paper will show the main results of calculation of the in-pile behaviour of two inert matrix oxide fuels dedicated to transmutation of Am in a fast spectrum ADS performed with MACROS. The results of the modelling studies show that designs of the fuel/target rods considered in FUTURE and MYRRHA projects (European projects for ADS transmuters) are quite suitable for long term operation under representative ADS conditions.",
keywords = "Oxide fuel, modelling, minor actinides, fuel performance, MACROS, MgO",
author = "Sergei Lemehov and Vitaly Sobolev and Kevin Govers and Marc Verwerft and {A{\"i}t Abderrahim}, Hamid",
note = "Score = 3; International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators ; Conference date: 04-05-2009 Through 08-05-2009",
year = "2009",
month = may,
day = "4",
language = "English",
booktitle = "International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators",

}

RIS - Download

TY - GEN

T1 - Progress and Advancements in Fuel Performance Modelling for MYRRHA/XT-ADS

AU - Lemehov, Sergei

AU - Sobolev, Vitaly

AU - Govers, Kevin

AU - Verwerft, Marc

AU - Aït Abderrahim, Hamid

N1 - Score = 3

PY - 2009/5/4

Y1 - 2009/5/4

N2 - Transmutation of the minor actinides (neptunium, plutonium, americium and curium) in either a fast reactor (FR) or a fast accelerator-driven system (ADS) is currently considered as one of the promising options. The current reference fuels for a European ADS-transmuter are oxides such as MOX, (Cm,Am,Pu)O2 diluted in MgO, ZrO2, and Mo matrices. In the framework of the number of EC projects and its own project MYRRHA, the Belgian Nuclear Research Centre SCK•CEN started few years ago the studies on fuels for transmutation in ADS. To evaluate basic in-pile features of fuel design the full-scale fuel performance code MACROS has been developed and is currently used. This paper will show the main results of calculation of the in-pile behaviour of two inert matrix oxide fuels dedicated to transmutation of Am in a fast spectrum ADS performed with MACROS. The results of the modelling studies show that designs of the fuel/target rods considered in FUTURE and MYRRHA projects (European projects for ADS transmuters) are quite suitable for long term operation under representative ADS conditions.

AB - Transmutation of the minor actinides (neptunium, plutonium, americium and curium) in either a fast reactor (FR) or a fast accelerator-driven system (ADS) is currently considered as one of the promising options. The current reference fuels for a European ADS-transmuter are oxides such as MOX, (Cm,Am,Pu)O2 diluted in MgO, ZrO2, and Mo matrices. In the framework of the number of EC projects and its own project MYRRHA, the Belgian Nuclear Research Centre SCK•CEN started few years ago the studies on fuels for transmutation in ADS. To evaluate basic in-pile features of fuel design the full-scale fuel performance code MACROS has been developed and is currently used. This paper will show the main results of calculation of the in-pile behaviour of two inert matrix oxide fuels dedicated to transmutation of Am in a fast spectrum ADS performed with MACROS. The results of the modelling studies show that designs of the fuel/target rods considered in FUTURE and MYRRHA projects (European projects for ADS transmuters) are quite suitable for long term operation under representative ADS conditions.

KW - Oxide fuel

KW - modelling

KW - minor actinides

KW - fuel performance

KW - MACROS

KW - MgO

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_96798

UR - http://knowledgecentre.sckcen.be/so2/bibref/5743

M3 - In-proceedings paper

BT - International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators

CY - Vienna, Austria

T2 - International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators

Y2 - 4 May 2009 through 8 May 2009

ER -

ID: 212052