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-1- UNRESTRICTED / ILLIMITÉ Corrosion and Deuterium Pickup in Zr-2.5Nb: Twenty Years of In-Reactor Testing at the OECD Halden Boiling Water Reactor H.M. Nordin, R. Szőke 19 th International Symposium on Zirconium in the Nuclear Industry May 19 - 23, 2019, Manchester, UK.

Corrosion and Deuterium Pickup in Zr-2.5Nb: Twenty Years ... · Twenty Years of In-Reactor Testing at the OECD Halden Boiling Water Reactor H.M. Nordin, R. Szőke ... Two vacuum arc

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Page 1: Corrosion and Deuterium Pickup in Zr-2.5Nb: Twenty Years ... · Twenty Years of In-Reactor Testing at the OECD Halden Boiling Water Reactor H.M. Nordin, R. Szőke ... Two vacuum arc

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Corrosion and Deuterium Pickup in Zr-2.5Nb:

Twenty Years of In-Reactor Testing at the OECD

Halden Boiling Water ReactorH.M. Nordin, R. Szőke

19th International Symposium on Zirconium in the Nuclear Industry

May 19 - 23, 2019, Manchester, UK.

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Outline

1. Introduction

• CANDU Reactor

• Pressure Tube

• Pressure Tube Fabrication

• Corrosion and Deuterium Ingress

2. Experiment

• Materials

• Test Loop

3. Results

4. Summary

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CANDU Reactor

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CANDU Reactor Fuel Channel

Pressuretube

Calandriatube

Feederpipe

Temperature

Flow

Fast neutron flux

[D]

•Temperature: 250°C – 310°C

•Pressure: 10 MPa

•Flux: 0 – 3.5x1017 n/m2s

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Pressure Tube Fabrication1990’s

Zirconium Feedstock

Two vacuum arc melts (Double Melt)

ingot

1960 – 1980’s

Press forge at 1015°CRotary forge at 815°C

Heat to 1015°C and β-Quench

Extrude at 815°C

Cold draw 27%

Steam Autoclave at 400C for 24 hours

1980’s

1970’s

Four vacuum arc melts (Quad Melt)

ingot

Press forge at 1015°CRotary forge at 815°C

Heat to 1015°C and β-Quench

Extrude at 815°C

Cold draw 27%

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Pressure Tubes• Historically, extensive research programs have been under

taken to fabricate improved pressure tubes:

• ~ 1960’s started investigating Zr-2.5Nb – improved mechanical properties and corrosion

• ~ 1980’s introduced β-quenching – improve strength

• ~ 1990’s introduced quad melting and lowered initial hydrogen content – reduce Cl and F for improved fracture toughness

• ~ 2000’s increased Fe concentration to 1080 ppm and reduced C concentration to 80 ppm – improve corrosion, deformation and fracture toughness

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Pressure Tubes• The extrusion process is known to result in microstructure and

texture variations along the pressure tube which in turn affects deformation, mechanical properties, oxidation and deuterium pickup.

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Corrosion and D Ingress• Corrosion and the associated deuterium ingress may be life

limiting degradation mechanisms in Zr-2.5Nb pressure tubes.

• Corrosion and deuterium uptake in pressure tubes can be influenced by:

- environmental factors (flux, temperature or pH).

- material properties (microstructure, microchemistry, texture and state of the β-phase) which are influenced by fabrication processes.

• To support pressure tube improvement programs, in-reactor corrosion and deuterium ingress studies were conducted at the OECD Halden Boiling Water Reactor over a 20 year period.

• Effect of environment and fabrication variables investigated:

- ingot melting (double melted or quadruple melted)- non--quenched versus -quenched- cold work (12% or 27%)- pH- In-flux versus out-flux

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Materials• Corrosion test coupons were machined from twenty-one different

Zr-2.5Nb pressure tubes.

- variations in fabrication history (e.g. β-quenched) and minor element concentration, illustrating the development history of pressure tube fabrication processes.

• The machined coupons tested had different surface finishes:

Machined coupons ~ 10 mm wide, 30 mm long and 1 mm thick

Machined

PickledHF, HNO3 and H2SO4 solution

Pickled + Pre-filmed400°C steam for 24 hours

Machined + Pre-filmed400°C steam for 24 hours

Note: Many variables!

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Schematic Diagram of In-Flux Test Loop 9

• Operates under CANDU HTS conditions (pHa 10.2-10.8)

• Two independently heated in-flux test channels, three out-flux autoclaves

• Temperature range: 250°C – 335°C

• Neutron flux: 3-5x1013 n/cm2/s

• Ratio of thermal flux\fast flux: 2:1

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Oxygen and Deuterium Pickup

• Oxidation kinetics were linear after 150 days.

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Effect of Flux on Oxide Growth Rate

• The in-flux oxide growth rate tends to be greater than the out-flux oxide growth rate (P-value = 0.0004).

• Enhancement of in-flux oxide growth rate dependent on initial microstructure and surface finish.

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• No effect of flux on deuterium pickup (P-value = 0.96).

Effect of Flux on D Pickup Rate

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• Oxide growth and deuterium pickup rate similar between Kroll and electrolytic.

• Larger extruded tube front-back differences in Kroll ingots.

Ingot Production

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Effect of Ingot Melting

• Quad melting result in lower deuterium ingress rates.

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Effect of β-Quenching

• β-quenching results in lower deuterium ingress rate.

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Effect of β-Quenching

Non-β-Quenched β-Quenched

• More uniform grain structure in β-quenched material.• Curly nature of non-β-quenched grains may cause β-Zr filaments to be

oriented perpendicular to free surface leading to faster oxidation along these filaments.

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Comparison of Fabrication Methods

• Fabrication modifications reduced oxide growth rate.

1960 - 1980 1980 - 1990 1990 - 2000 2000 - 2005

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Comparison of Fabrication Methods

1960 - 1980 1980 - 1990 1990 - 2000 2000 - 2005

• Deuterium ingress reduced by a factor of 5.

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Discussion• A large number of confounding variables in tests making

comparison of data and interpretation of the results difficult.

• The synergistic interactions between fabrication processes, microstructure, texture, the state of the β-phase and the resulting pressure tube properties are difficult to assess.

• With the tube improvements, the net total concentration of hydrogen isotopes has been significantly reduced making Zr-2.5Nb pressure tubes much less susceptible to the deleterious effects of hydrides on fracture properties.

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Conclusions• Research programs undertaken to improve pressure tube

properties were successful in reducing corrosion and deuterium ingress.

• Deuterium ingress reduced by a factor of 5.

• This reduction should make Zr-2.5Nb pressure tubes much less susceptible to the deleterious effects of hydrides on fracture properties.

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Acknowledgements• CNL’s (formerly AECL’s) in-reactor corrosion test program lasted for

approximately 20 years. • The contributions of many individuals need to be acknowledged:

• From AECL/CNL (including former employees): V. F. Urbanic, R.A. Ploc, G. McDougall, I. J. Muir, G.A. McRae, A. A. Bahurmuz, A.J. Elliott, A. Shaddick, S. Bergin, V. Hilton, C. Davis, M. Seguin, D. Wilkins, R. MacLeod, A. Britton, R. Stuthers, P. Sullivan, D. Irvine, R. Beier, J. Hamel, Y. Andrews and M. Godin.

• From the Halden Reactor Project (including former employees): M. A. McGrath, K-L Moum, I. Thoresen, H. Devold, H. Valseth, H. Thoresen, C. Helsengreen, M. Lundgren, K-W. Eriksen, C. Vitanza.