On the critical mechanisms for the embrittlement and strength degradation of post-irradiated U-10Mo fuels-Reference-Cited by-同舟云学术

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On the critical mechanisms for the embrittlement and strength degradation of post-irradiated U-10Mo fuels

Published:2024-09 Issue: Volume: Page:110474
ISSN:0013-7944
Container-title:Engineering Fracture Mechanics
language:en
Short-container-title:Engineering Fracture Mechanics

Author:

Jin Chaoyue,Ding Guochen,Jian Xiaobin,Zhang Jing,Li Yong,Ding Shurong

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Reference45 articles.

1. Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel;Meyer;J Nucl Mater,2002

2. Irradiation behavior of atomized U–10wt.% Mo alloy aluminum skeleton dispersion fuel meat at low temperature;Kim;Nucl Engng Des,2002

3. Fabrication of monolithic RERTR fuels by Hot Isostatic Pressing;Jue;Nucl Technol,2010

4. A mesoscale stress model for irradiated U10Mo monolithic fuels based on evolution of volume fraction/radius/internal pressure of bubbles;Jian;Nucl Engng Technol,2019

5. Mechanical properties of irradiated UMo alloy fuel;Schulthess;J Nucl Mater,2019

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