26.08.2015   Materials' ageing and degradation in. light water reactors

Sources of further information

Major sources are many, including:

• ZIRAT Annual Reports and ZIRAT Special Topic Reports, A. N.T. International, Molnlycke, Sweden (www. antinternational. com).

Table 4.11 Material variations being used in or considered for PWR fuel bundle components

Alloy

Sn (%)

Nb (%)

Fe (%)

Cr (%)

Others

Cond.*

FF**

HPUF (%)***

Modif. Zry-4

1.3

0.3

0.2

PR/RX

~1.8/2.3

-/12

NDA

1

0.1

0.3

0.2

SR

~2.4

15/-

S2

0.8

0.1

0.3

0.1

RX

~2.2

DX ELS 0.8B

0.8

0.3

0.2

SR

~1.1

-/24

DX D4

0.5

0.5

0.2

SR

~1

-/20

HPA-4

0.5

0.5

0.3V

SR/RX

-1/1.3

-/10

E635

1.3

1

0.4

RX

ZIRLO

1

1

0.1

SR/RX

~2.4

15/-

MDA

0.8

0.5

0.2

0.1

SR

-2.4

15/-

Low-Sn-ZIRLO

0.7

1

0.1

SR

-1.4

15/-

Optim. ZIRLO

0.67

1

0.1

PR

-1.9

15/-

M-MDA

0.5

0.5

0.4

0.3

SR/RX

-1.4/2.5

Quart-NbSnFe

0.5

1

0.1

RX

-2

-/>30

AXIOM X5A

0.45

0.3

0.35

0.25

50%PR

-1.6

HANA-4

0.4

1.5

0.2

0.1

PR

-1.6

AXIOM-X1

0.3

0.7-1

0.05

0.12Cu, 0.2V

80%PR

-1.3

AXIOM-X5

0.3

0.7

0.35

0.25

50%PR

-0.9

Quart-NbFeSn

0.3

1

0.1

RX

-1.4

10

Quart-NbFeSn

0.3

1

0.2

RX

-1.2

10

E110

1

0.01

RX

-0.8

<10

M5

1

0.04

20ppm S

RX

-0.8

<10

Quart-NbFe

1

01

RX

-0.6

AXIOM-X2

1

0.06

RX

-1

AXIOM-X4

1

0.06

0.25

0.05Cu

80%PR

-0.8

HANA-6

1.1

0.05Cu

PR

-1.3

J-Alloys

1.6-2.5

0-0.01

PNb

RX

-0.9

* PR, partially recrystallized; RX, recrystallized; SR, stress relieved. ** Fitting factor (calculated by Garzarolli et al., 2011a).

*** Hydrogen pickup fraction (calculated by Garzarolli et al., 2011a). Source: Garzarolli et al. (2011a).

Table 4.12 Material variations being used or considered for BWR channels

Material Composition Proposed advantage

C SC

HPUF

HPUF HB

G

Reference

Zry-4

Zr-1.3Sn-0.2Fe-0.1Cr

x

x

x

Cantonwine et al.,

2008; AREVA

NSF

Zr-1Nb-1Sn-0.35Fe

x

x

x

x

Ledford et al., 2010;

Kobylyansky et al., 2010

VB

Zr-0.5Sn-1Cr-0.5Fe

x

x

x

Vaidyanathan et al., 2000

ZIRLO

Zr-1Nb-1Sn-0.1Fe

x

x

x

x

Helmersson & Dag, 2008

PQ Zry-4

Zr-1.3Sn-0.2Fe-0.1Cr

x

x

Sedano et al., 2010

PQ Zry-2

Zr-1.3Sn-0.17Fe-0.1Cr

x

Dahlback et al., 2005;

Mockel et al., 2008

Notes: Proposed advantage relative to current Zry-2; C — corrosion; SC — shadow corrosion; HPUF — hydrogen pickup fraction; HPUF HB — at high burnup; G — irradiation growth; PQ — beta quenched.

Source: A. N.T International (2011) and Garzarolli et al. (2011a).

• The series of Zirconium in the Nuclear Industry, International Symposiums, ASTM International, West Conshohocken, PA, USA, held every 2-3 years.

• Zirconium Production and Technology: The Kroll Medal Papers 1985­2010, editor, R. B. Adamson, ASTM International RPS2, ASTM I, West Conshohocken, PA, USA, 2010.

• Proceedings of the LWR Fuel Performance Meeting/Top Fuel/WRFPM, held annually in the United States, Europe or Asia.

• References given in Section 4.10

• The next chapter of this book — ‘Performance and Inspection of Zirconium Alloy Components in Nuclear Power Light Water Reactors’ P. Rudling, ANT International, Molnlycke, Sweden and R. B. Adamson, Zircology Plus, Fremont, CA, USA.

4.7 Acknowledgements

The authors sincerely thank our colleagues in the expert network staff of

ANT International: Brian Cox, Friedrich Garzarolli, Charles Patterson and

Alfred Strasser. Their discussions, their expertise, their comments and their

contributions to the ZIRAT programme reports have greatly contributed

to this chapter.