Dynamic finite element modeling of the effects of size on the upper shelf energy of pressure vessel steels
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Research context
OpenAlex topics: Fatigue and fracture mechanics · Engineering Structural Analysis Methods · Structural Load-Bearing Analysis
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References (23)
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1. Corwin · J. Nucl. Mater. · 1984 · 122&123 · 34310.1016/0022-3115(84)90622-6 ↗
2. The Use Small Scale Specimens f for Testing Irradiated Material
3. Ferguson · 1978 · 90
4. Abe · J. Nucl. Mater. · 1987 · 150 · 29210.1016/0022-3115(87)90007-9 ↗
5. The Use of Small-Scale Specimens for Testing Irradiated Material
6. Lucas · Fusion Technol. · 1986 · 10 · 72810.13182/FST86-A24827 ↗
7. Louden · J. Nucl. Mater. · 1988 · 155–157 · 66210.1016/0022-3115(88)90391-1 ↗
8. Kumar · 1990 · 487
9. Rosinski · 1993 · 1204 · 405
10. Effect of Radiation on Materials
11. Kayano · J. Nucl. Mater. · 1991 · 179–181 · 42510.1016/0022-3115(91)90115-N ↗
12. Specimen Size Effects in Charpy Impact Testing
13. Amayev · 1993 · 1204 · 424
14. Kurishita · Mater. Trans. · 1993 · 34 · 104210.2320/matertrans1989.34.1042 ↗
15. Kumar · J. Nucl. Mater. · 1995 · 225 · 23810.1016/0022-3115(95)00050-X ↗
16. Schubert · J. Nucl. Mater. · 1995 · 225 · 23110.1016/0022-3115(95)00052-6 ↗
17. Kurishita · J. Nucl. Mater. · 1994 · 212–215 · 168210.1016/0022-3115(94)91113-4 ↗
18. Kurishita · Mater. Trans. JIM · 1993 · 34 · 104210.2320/matertrans1989.34.1042 ↗
19. Fracture of Structure Materials
20. Hibbit, Karlsson and Sorensen, Incorporated · ABAQUS Explicit Users Manual Ver. 5.4, HKS · 1995
21. Sidener · 1995
22. Nuclear Pressure Vessel Steel Data Base
23. In-Situ Measurements of Mechanical Properties Using Novel Automated Ball Indentation System, Small Specimen Test Techniques Applied to Nuclear Reactor Ves sel Thermal Annealing and Plant Life Extension