Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings-Reference-Cited by-同舟云学术

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Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings

Published:2019-04 Issue: Volume:516 Page:347-353
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Yano Y.,Sekio Y.,Tanno T.,Kato S.,Inoue T.,Oka H.,Ohtsuka S.,Furukawa T.,Uwaba T.,Kaito T.,Ukai S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference28 articles.

1. Burst properties of irradiated oxide dispersion strengthened ferritic steel claddings

2. Ring-tensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings

3. Effects of neutron irradiation on tensile properties of oxide dispersion strengthened (ODS) steel claddings

4. In-pile creep rupture properties of ODS ferritic steel claddings

5. Irradiation response of ODS Eurofer97 steel

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1. Study on the safety performance of an offshore stationary lead-cooled fast reactor design loaded with nitride fuel;Annals of Nuclear Energy;2024-12

2. Formulation of high-temperature strength equation of 9Cr-ODS tempered martensitic steels using the Larson–Miller parameter and life-fraction rule for rupture life assessment in steady-state, transient, and accident conditions of fast reactor fuel;Journal of Nuclear Materials;2024-05

3. Small punch test for investigating circumferential creep in cladding tubes;International Journal of Mechanical Sciences;2024-04

4. Transients Analysis of the Offshore Fixed Multi-Purpose Integrated All-Natural-Cycle Small Lead-Cooled Reactor with the Frtac Code;2024

5. Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C;Journal of Nuclear Science and Technology;2023-10-19

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