Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor

Brian Boer; Sergei Lemehov; Vitaly Sobolev; Marc Verwerft; Kevin Govers

Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor

Brian Boer, Sergei Lemehov, Vitaly Sobolev, Marc Verwerft, Kevin Govers

Research output › peer-review

Abstract

The assessment of the (safety-related) performance of the driver fuel rods of the reactor is of key importance to the licensing process of MYRRHA, which is currently in its “pre-licensing” phase. Although the fuel rod design is largely based on past (sodium) fast reactor experience, the use of LBE as the coolant requires a thorough re-evaluation of the fuel design for specific MYRRHA conditions. This paper presents preliminary results.

Original language	English
Title of host publication	TRANSACTIONS- AMERICAN NUCLEAR SOCIETY
Place of Publication	United States
Pages	1201-1204
State	Published - 1 Apr 2012
Event	2012 American Nuclear Society annual meeting - Chicago Duration: 23 Jun 2012 → 29 Jun 2012

Conference

Conference	2012 American Nuclear Society annual meeting
Country/Territory	United States
City	Chicago
Period	2012-06-23 → 2012-06-29

Cite this

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title = "Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor",

abstract = "The assessment of the (safety-related) performance of the driver fuel rods of the reactor is of key importance to the licensing process of MYRRHA, which is currently in its “pre-licensing” phase. Although the fuel rod design is largely based on past (sodium) fast reactor experience, the use of LBE as the coolant requires a thorough re-evaluation of the fuel design for specific MYRRHA conditions. This paper presents preliminary results.",

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AB - The assessment of the (safety-related) performance of the driver fuel rods of the reactor is of key importance to the licensing process of MYRRHA, which is currently in its “pre-licensing” phase. Although the fuel rod design is largely based on past (sodium) fast reactor experience, the use of LBE as the coolant requires a thorough re-evaluation of the fuel design for specific MYRRHA conditions. This paper presents preliminary results.

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KW - fuel performance

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UR - http://knowledgecentre.sckcen.be/so2/bibref/12432

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BT - TRANSACTIONS- AMERICAN NUCLEAR SOCIETY

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