Evaluation of alloy 690 process pot at the contact with borosilicate melt pool during vitrification of high-level nuclear waste

被引：32

作者：

Sengupta, Pranesh ^{[1
]}

Kaushik, C. P. ^{[2
]}

Kale, G. B. ^{[1
]}

Das, D. ^{[3
]}

Raj, K. ^{[3
]}

Sharma, B. P. ^{[4
]}

机构：

[1] Bhabha Atom Res Ctr, Div Mat Sci, Bombay 400085, Maharashtra, India

[2] Bhabha Atom Res Ctr, Waste Management Div, Bombay 400085, Maharashtra, India

[3] Bhabha Atom Res Ctr, Div Chem, Bombay 400085, Maharashtra, India

[4] Bhabha Atom Res Ctr, Chem Engn Grp, Bombay 400085, Maharashtra, India

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 392卷 / 03期

关键词：

CORROSION; EVOLUTION; INCONEL;

D O I：

10.1016/j.jnucmat.2008.07.046

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Understanding the material behaviour under service conditions is essential to enhance the life span of alloy 690 process pot used in vitrification of high-level nuclear waste. During vitrification process, interaction of alloy 690 with borosilicate melt takes place for substantial time period. Present experimental studies show that such interactions may result in Cr carbide precipitation along grain boundaries, Cr depletion in austenitic matrix and intergranular attack close to alloy 690/borosilicate melt pool interfaces. Widths of Cr depleted zone within alloy 690 is found to follow kinetics of the type x = 10.9 x 10(-6) + 1 x 10(-8)t(1/2) m. Based on the experimental results it is recommended that compositional modification of alloy 690 process pot adjacent to borosilicate melt pool need to be considered seriously for any efforts towards reduction and/or prevention of process pot failures. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：379 / 385

页数：7

共 15 条

[1]

[Anonymous], PIT201 INSAC KALP

[2] LOW-TEMPERATURE STRESS-CORROSION CRACKING OF INCONEL-600 UNDER 2 DIFFERENT CONDITIONS OF SENSITIZATION [J].

BANDY, R ;

ROBERGE, R ;

NEWMAN, RC .

CORROSION SCIENCE, 1983, 23 (09) :995-1006

[3] Microstructural and corrosion aspects of alloy 690 [J].

Dutta, RS ;

Tewari, R .

BRITISH CORROSION JOURNAL, 1999, 34 (03) :201-205

[4]

Imrich KJ., 2000, CERAM T, V107, P643

[5]

IVERSON DC, 2004, CERAM T, V155, P217

[6]

JANTZEN CM, CERAM T, P31

[7] THE EFFECTS OF HEAT-TREATMENT ON THE CHROMIUM DEPLETION, PRECIPITATE EVOLUTION, AND CORROSION RESISTANCE OF INCONEL ALLOY-690 [J].

KAI, JJ ;

YU, GP ;

TSAI, CH ;

LIU, MN ;

YAO, SC .

METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1989, 20 (10) :2057-2067

[8] Case reviews on the effect of microstructure on the corrosion behavior of austenitic alloys for processing and storage of nuclear waste [J].

Kain, V ;

Sengupta, P ;

De, PK ;

Banerjee, S .

METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2005, 36A (05) :1075-1084

[9] Barium borosilicate glass - a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste [J].

Kaushik, C. P. ;

Mishra, R. K. ;

Sengupta, P. ;

Kumar, Arnar ;

Das, D. ;

Kale, G. B. ;

Raj, Kanwar .

JOURNAL OF NUCLEAR MATERIALS, 2006, 358 (2-3) :129-138

[10] The effect of grain boundary misorientation on the intergranular M23C6 carbide precipitation in thermally treated Alloy 690 [J].

Lim, YS ;

Kim, JS ;

Kim, HP ;

Cho, HD .

JOURNAL OF NUCLEAR MATERIALS, 2004, 335 (01) :108-114

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