Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding

被引：6

作者：

Ridley, Mackenzie ^{[1
]}

Bell, Samuel ^{[1
,2
]}

Garrison, Ben ^{[1
]}

Graening, Tim ^{[1
]}

Capps, Nathan ^{[1
]}

Su, Yi-Feng ^{[1
]}

Mouche, Peter ^{[1
,3
]}

Johnston, Brandon ^{[1
]}

Kane, Kenneth ^{[1
,4
]}

机构：

[1] Oak Ridge Natl Lab, Oak Ridge, TN 37830 USA

[2] Univ Tennessee, Dept Mat Sci & Engn, Knoxville, TN USA

[3] Argonne Natl Lab, Lemont, IL USA

[4] Johns Hopkins Univ, Appl Phys Lab, Laurel, MD USA

来源：

ANNALS OF NUCLEAR ENERGY | 2023年 / 188卷

基金：

美国能源部;

关键词：

Accident tolerant fuel; LOCA; Chromium coatings; Zircaloy-4; HiPIMS; Cladding; HIGH-TEMPERATURE OXIDATION; CR-COATED ZIRCALOY-4; ZIRCONIUM; BEHAVIOR; PROPERTY; ALLOYS;

D O I：

10.1016/j.anucene.2023.109799

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Cr-coated zirconium alloys represent a modern approach to enhance cladding safety during accident scenarios. Two high-power impulse magnetron sputtered Cr-coated Zry-4 systems were subjected to simulated loss-of-coolant accident conditions to investigate cladding performance. The first Cr-coating (4.8 mu m thick) was deposited onto Zry-4 cladding and exhibited through-thickness cracking while the second Cr-coating (6.8 mu m thick) was deposited with improved deposition parameters onto polished Zry-4 and exhibited no cracking. During burst testing, the coating with a higher density of defects failed to consistently reduce oxidation and exhibited similar burst behavior as Zry-4. In contrast, the second Cr-coating reduced ZrO2 formation through formation of Cr2O3 and displayed enhanced burst temperatures by similar to 80 degrees C compared to Zry-4. Utilizing an empirical relation for burst behavior of zirconium alloys, the 6.8 mu m Cr/Zry-4 system displayed enhanced burst temperatures equivalent to an effective 0.464 mm increase in Zry-4 wall thickness, highlighting the value of continuous Cr coatings for accident scenarios.

引用

页数：10

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