Length scale effects of micro- and meso-scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

被引：0

作者：

Lam, S. ^{[1
]}

Frazer, D. ^{[2
]}

Cappia, F. ^{[2
]}

Nelson, M. ^{[1
,2
]}

Samuha, S. ^{[3
]}

Pitts, S. ^{[2
]}

Harris, B. ^{[2
]}

Hosemann, P. ^{[4
]}

机构：

[1] Univ Calif Berkeley, Dept Nucl Engn, Berkeley, CA USA

[2] Idaho Natl Lab, Idaho Falls, ID USA

[3] NCRN, Dept Mat Engn, Beer Sheva, Israel

[4] Univ Calif Berkeley, Dept Mech Engn, Berkeley, CA USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2025年 / 604卷

关键词：

Zircaloy; Fuel cladding; Tensile testing; Small scale mechanical testing; MECHANICAL-PROPERTIES;

D O I：

10.1016/j.jnucmat.2024.155469

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Zircaloy-4 is an essential material for cladding structures within fission-based reactors. To explore the changes in properties measured on differing length scales, FIB-machined micro-scale tensile tests were performed on both irradiated and control groups of Zircaloy-4. This was correlated with tensile testing on femtosecond lasermachined meso-scale specimens. Pronounced size effects were found when varying specimen geometry. Increases in tensile geometry size were associated with a reduction in measured yield stress for both irradiated and unirradiated samples. Meso-scale testing found strength and strain values similar to that of bulk-scale testing.

引用

页数：7

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