Development of advanced expansion due to compression (A-EDC) test method for safety evaluation of degraded nuclear fuel cladding materials-Reference-Cited by-同舟云学术

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Development of advanced expansion due to compression (A-EDC) test method for safety evaluation of degraded nuclear fuel cladding materials

Published:2015-07-29 Issue:10 Volume:52 Page:1232-1239
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Abe Hiroaki,Abe Tomonori,Kishita Shiori,Kano Sho,Li Yanfen,Yang Huilong,Tawara Kyosuke,Matsukawa Yoshitaka,Satoh Yuhki

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/00223131.2015.1056560

Reference24 articles.

1. Preferential precipitation of hydrides in textured zircaloy-4 sheets

2. Evaluation of Hydride Reorientation Behavior and Mechanical Properties for High-Burnup Fuel-Cladding Tubes in Interim Dry Storage

3. Neutron damage in zirconium alloys irradiated at 644 to 710 k

4. The PROMETRA Program: Fuel Cladding Mechanical Behavior under High Strain Rate

5. Effects of oxide and hydrogen on the circumferential mechanical properties of Zircaloy-4 cladding

Cited by 14 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Workshop on development of accident tolerant fuel for light water reactor;Journal of the Atomic Energy Society of Japan;2024

2. Modeling and tests on the damage and fracture behaviors of non-irradiated zirconium alloys with different hydrogen concentrations at RT and 350°C;Journal of Nuclear Materials;2023-12

3. A plasma-based pressure pulse generator for simulating pellet–cladding mechanical interaction during reactivity-initiated accident;Review of Scientific Instruments;2023-08-01

4. Flow Stress Modeling of Tube and Slab Route Sheets of Zircaloy-4 Using Machine Learning Techniques and Arrhenius Type Constitutive Equations;Journal of Materials Engineering and Performance;2022-08-12

5. Expansion deformation behavior of zirconium alloy claddings with different hydrogen concentrations;Journal of Nuclear Materials;2021-10

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