Compatibility of structural materials with liquid lead-bismuth eutectic

Research output: ThesisDoctoral thesis

Standard

Compatibility of structural materials with liquid lead-bismuth eutectic. / Sapundjiev, Danislav; Van Dyck, Steven (Peer reviewer).

Leuven, Belgium : KUL - Katholieke Universiteit Leuven, 2007. 160 p.

Research output: ThesisDoctoral thesis

Harvard

Sapundjiev, D & Van Dyck, S 2007, 'Compatibility of structural materials with liquid lead-bismuth eutectic', KUL - Katholieke Universiteit Leuven , Leuven, Belgium.

Vancouver

Sapundjiev D, Van Dyck S. Compatibility of structural materials with liquid lead-bismuth eutectic. Leuven, Belgium: KUL - Katholieke Universiteit Leuven, 2007. 160 p.

Author

Sapundjiev, Danislav ; Van Dyck, Steven. / Compatibility of structural materials with liquid lead-bismuth eutectic. Leuven, Belgium : KUL - Katholieke Universiteit Leuven, 2007. 160 p.

Bibtex - Download

@phdthesis{f263d0e19cfc4ba396836bb7792841f5,
title = "Compatibility of structural materials with liquid lead-bismuth eutectic",
abstract = "In recent years interest in Heavy Liquid Metal Coolants was revived owing to the development of Generation IV nuclear reactors, experimental and demonstration fusion reactors and accelerator driven nuclear systems. The goal of this work is to investigate the effects of liquid lead bismuth eutectic (LBE) on the engineering properties (namely strength and ductility) of several materials, martensitic steel T91 and austenitic steel AISI316L. The research started with investigation on the general liquid metal corrosion effects. At higher temperatures T91 had a better corrosion resistance than A316L and conversely below this temperature A316L material corroded at much lower rates. Parallel with this experiment, an installation for mechanical tests in liquid LBE was designed and constructed. No experimental evidence was observed that the investigated materials are sensitive to liquid metal embrittlement (LME) in their as received condition. At the beginning of this work no experimental data was available about the effect of both liquid metal and particle irradiation on the metal properties. Therefore a primary concern was the irradiation induced hardening of T91. The obtained results unequivocally show that neither T91 nor other ferritic martensitic steels selected for Gen IV or other advanced liquid metal reactors are sensitive to LME.",
keywords = "Heavy liquid metal coolants, corrosion, embrittlement",
author = "Danislav Sapundjiev and {Van Dyck}, Steven",
note = "Score = 30",
year = "2007",
month = mar,
day = "12",
language = "English",
isbn = "978-90-5682-759-5",
publisher = "KUL - Katholieke Universiteit Leuven",
school = "KUL - Katholieke Universiteit Leuven ",

}

RIS - Download

TY - THES

T1 - Compatibility of structural materials with liquid lead-bismuth eutectic

AU - Sapundjiev, Danislav

A2 - Van Dyck, Steven

N1 - Score = 30

PY - 2007/3/12

Y1 - 2007/3/12

N2 - In recent years interest in Heavy Liquid Metal Coolants was revived owing to the development of Generation IV nuclear reactors, experimental and demonstration fusion reactors and accelerator driven nuclear systems. The goal of this work is to investigate the effects of liquid lead bismuth eutectic (LBE) on the engineering properties (namely strength and ductility) of several materials, martensitic steel T91 and austenitic steel AISI316L. The research started with investigation on the general liquid metal corrosion effects. At higher temperatures T91 had a better corrosion resistance than A316L and conversely below this temperature A316L material corroded at much lower rates. Parallel with this experiment, an installation for mechanical tests in liquid LBE was designed and constructed. No experimental evidence was observed that the investigated materials are sensitive to liquid metal embrittlement (LME) in their as received condition. At the beginning of this work no experimental data was available about the effect of both liquid metal and particle irradiation on the metal properties. Therefore a primary concern was the irradiation induced hardening of T91. The obtained results unequivocally show that neither T91 nor other ferritic martensitic steels selected for Gen IV or other advanced liquid metal reactors are sensitive to LME.

AB - In recent years interest in Heavy Liquid Metal Coolants was revived owing to the development of Generation IV nuclear reactors, experimental and demonstration fusion reactors and accelerator driven nuclear systems. The goal of this work is to investigate the effects of liquid lead bismuth eutectic (LBE) on the engineering properties (namely strength and ductility) of several materials, martensitic steel T91 and austenitic steel AISI316L. The research started with investigation on the general liquid metal corrosion effects. At higher temperatures T91 had a better corrosion resistance than A316L and conversely below this temperature A316L material corroded at much lower rates. Parallel with this experiment, an installation for mechanical tests in liquid LBE was designed and constructed. No experimental evidence was observed that the investigated materials are sensitive to liquid metal embrittlement (LME) in their as received condition. At the beginning of this work no experimental data was available about the effect of both liquid metal and particle irradiation on the metal properties. Therefore a primary concern was the irradiation induced hardening of T91. The obtained results unequivocally show that neither T91 nor other ferritic martensitic steels selected for Gen IV or other advanced liquid metal reactors are sensitive to LME.

KW - Heavy liquid metal coolants

KW - corrosion

KW - embrittlement

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_89171

M3 - Doctoral thesis

SN - 978-90-5682-759-5

PB - KUL - Katholieke Universiteit Leuven

CY - Leuven, Belgium

ER -

ID: 378835