Swelling of 20% Cold-Worked Type 316 Stainless Steel Fuel Pin Cladding and Ducts
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ASTM International
Cited by 4 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. Tensile properties of modified 316 stainless steel (PNC316) after neutron irradiation over 100 dpa;Journal of Nuclear Science and Technology;2023-08-11
2. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure;Journal of Nuclear Materials;2000-01
3. A third stage of irradiation creep involving its cessation at high neutron exposures;Journal of Nuclear Materials;1987-05
4. New developments in irradiation-induced microstructural evolution of austenitic alloys and their consequences on mechanical properties;Radiation Effects;1987-01
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