Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor

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

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Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor. / Boer, Brian; Lemehov, Sergei; Sobolev, Vitaly; Verwerft, Marc; Govers, Kevin (Peer reviewer).

TRANSACTIONS- AMERICAN NUCLEAR SOCIETY. United States, 2012. p. 1201-1204.

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

Harvard

Boer, B, Lemehov, S, Sobolev, V, Verwerft, M & Govers, K 2012, Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor. in TRANSACTIONS- AMERICAN NUCLEAR SOCIETY. United States, pp. 1201-1204, 2012 American Nuclear Society annual meeting, Chicago, United States, 2012-06-23.

APA

Vancouver

Boer B, Lemehov S, Sobolev V, Verwerft M, Govers K. Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor. In TRANSACTIONS- AMERICAN NUCLEAR SOCIETY. United States. 2012. p. 1201-1204

Bibtex - Download

@inproceedings{9fe978bcf14648c2bc81ebcdfc2ad041,
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.",
keywords = "MYRRHA, fuel performance",
author = "Brian Boer and Sergei Lemehov and Vitaly Sobolev and Marc Verwerft and Kevin Govers",
note = "Score = 3",
year = "2012",
month = "4",
day = "1",
language = "English",
pages = "1201--1204",
booktitle = "TRANSACTIONS- AMERICAN NUCLEAR SOCIETY",

}

RIS - Download

TY - GEN

T1 - Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor

AU - Boer, Brian

AU - Lemehov, Sergei

AU - Sobolev, Vitaly

AU - Verwerft, Marc

A2 - Govers, Kevin

N1 - Score = 3

PY - 2012/4/1

Y1 - 2012/4/1

N2 - 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.

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.

KW - MYRRHA

KW - fuel performance

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_138900

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

M3 - In-proceedings paper

SP - 1201

EP - 1204

BT - TRANSACTIONS- AMERICAN NUCLEAR SOCIETY

CY - United States

ER -

ID: 246776