Properties of zirconium alloys and their applications in light water reactors (LWRs) - Materials' Ageing and Degradation in Light Water Reactors - page 92

Table 4.3 Commercial Zr base materials currently used for zirconium alloy fuel components in PWRs, BWRs, VVERs and RBMKs
(Cox et al ., 2006)

Alloy Sn % Nb % Fe % Cr % Ni % O % Fuel vendor

BWRs
Zircaloy-2 (SRA a /(RXA b )

1.2-1.7 - 0.07-0.2 0.05-0.15 0.03-0.08 0.1-0.14 All fuel vendors

Zr-Liner b
Sponge

- - 0.015-0.06 - - 0.05-0.1 Only used in Japan and Russia

ZrSn 0.25 - 0.03-0.06 - - 0.05-0.1 W

ZrFe - - 0.4 - - 0.05-0.1 AREVA

ZrFe - - 0.10 - - 0.05-0.1 GNF c

PWRs
Zircaloy-4 (SRA) 1.2-1.7 - 0.18-0.24 0.07-0.13 - 0.1-0.14

ZIRLO (SRA) 1 1 0.1 - - 0.12 W

Optimized ZIRLO (SRA/pRXA d ) 0.7 1 0.1 - - 0.12 W

M5 (RXA) - 0.8-1.2 0.015-0.06 - - 0.09-0.12 AREVA

HPA-4 e (SRA/RXA) 0.6 - Fe+V - - 0.12 AREVA

NDA f (SRA) 1 0.1 0.3 0.2 0.12 NFI g

MDA h (SRA) 0.8 0.5 0.2 0.1 0.12 MHI i

VVER, RBMK
E110 (RXA) - 0.9-1.1 0.014 <0.003 0.0035 0.05-0.07 Fuel cladding

Alloy E125 (SRA) - 2.5 - - - 0.06 Structural components

a Stress relieved annealed.
b Recrystallized annealed.
c Global nuclear fuel.
d Partially recrystallized condition.
e High performance alloy.
f New developed alloy.
g Nuclear fuel industries.
h Mitsubishi developed alloy.
i Mitsubishi heavy industries.