Corrosion, Al containing corrosion barriers and mechanical properties of steels foreseen as structural materials in liquid lead alloy cooled nuclear systems

被引:43
作者
Weisenburger, Alfons [1 ]
Mueller, Georg [1 ]
Heinzel, Annette [1 ]
Jianu, Adrian [1 ]
Muscher, Heinrich [1 ]
Kieser, Martin [1 ]
机构
[1] KIT, Inst Pulsed Power & Microwave Technol IHM, D-76344 Eggenstein Leopoldshafen, Germany
关键词
CYCLE FATIGUE BEHAVIOR; METAL EMBRITTLEMENT; MARTENSITIC STEEL; BISMUTH; T91; TEMPERATURE; TESTS; OXIDATION; LBE;
D O I
10.1016/j.nucengdes.2010.08.005
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A key problem in development of heavy liquid metal cooled nuclear energy and transmutation reactors is the corrosion of structural and fuel. Above 500 degrees C steels have to be protected by stable, thin oxide scales. A well understood measure is alloying of stable oxide formers into the surface. Two methods, alloying an Al layer into the steel surface using pulsed electron beams (GESA - gepulste Elektronenstrahlanlage) and coating the surface with an Al-alloy with subsequent GESA treatment are applied. In the range of 4-10 wt% Al on the surface a stable thin alumina scale is formed by Al diffusion to the surface and selective oxidation. The alumina scale grows only very slowly and prevents migration of oxygen into the steel as well as migration of steel components onto the surface. A number of corrosion experiments showed the good protective behaviour of Al scales in LBE with 10(-6) wt% oxygen up to 650 degrees C and for exposure times up to 10,000 h. Furthermore the influence of parameters like stresses in the cladding wall, creep behaviour, different flow velocities of the LBE and changing temperatures and oxygen concentrations in LBE is discussed. This paper will provide an overview on the activities concerning Pb-PbBi corrosion and corrosion protection performed at the Institute of Pulsed Power and Microwave Technology (IHM) at the KIT. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:1329 / 1334
页数:6
相关论文
共 24 条
[1]  
BALLINGER R, 2003, P 11 INT C NUCL ENG
[2]  
Chapman L.A., 2005, 018 NPL DECPMPE
[3]  
Courouau J.-L., 2007, HDB LEAD BISMUTH EUT, p129ff
[4]   Pulsed electron beam facility (GESA) for surface treatment of materials [J].
Engelko, V ;
Yatsenko, B ;
Mueller, G ;
Bluhm, H .
VACUUM, 2001, 62 (2-3) :211-216
[5]   Compatibility tests on steels in molten lead and lead-bismuth [J].
Fazio, C ;
Benamati, G ;
Martini, C ;
Palombarini, G .
JOURNAL OF NUCLEAR MATERIALS, 2001, 296 :243-248
[6]   Corrosion behavior of FBR candidate materials in stagnant Pb-Bi at elevated temperature [J].
Furukawa, T ;
Müller, G ;
Schumacher, G ;
Weisenburger, A ;
Heinzel, A ;
Zimmermann, F ;
Aoto, K .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (03) :265-270
[7]   Creep-to-rupture tests of T91 steel in flowing Pb-Bi eutectic melt at 550 °C [J].
Jianu, A. ;
Mueller, G. ;
Weisenburger, A. ;
Heinzel, A. ;
Fazio, C. ;
Markov, V. G. ;
Kashtanov, A. D. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 394 (01) :102-108
[8]   Influence of PbBi environment on the low-cycle fatigue behavior of SNS target container materials [J].
Kalkhof, D ;
Grosse, M .
JOURNAL OF NUCLEAR MATERIALS, 2003, 318 :143-150
[9]   Corrosion studies in liquid Pb-Bi alloy at JAERI: R&D program and first experimental results [J].
Kurata, Y ;
Futakawa, A ;
Kikuchi, K ;
Saito, S ;
Osugi, T .
JOURNAL OF NUCLEAR MATERIALS, 2002, 301 (01) :28-34
[10]   Liquid metal embrittlement of the martensitic steel 91: influence of the chemical composition of the liquid metal. Experiments and electronic structure calculations [J].
Legris, A ;
Nicaise, G ;
Vogt, JB ;
Foct, J .
JOURNAL OF NUCLEAR MATERIALS, 2002, 301 (01) :70-76