Development of Small Specimen Technique to Evaluate Ductile–Brittle Transition Behavior of a Welded Reactor Pressure Vessel Steel
Author:
Publisher
Springer Japan
Link
http://link.springer.com/content/pdf/10.1007/978-4-431-99779-5_48
Reference7 articles.
1. Schubert LE, Kumar AS, Rosinski ST, Hamilton ML (1995) Effect of specimen size on the impact properties of neutron irradiated A533B steel. J Nucl Mater 225:231–237
2. Liu C, Bhole SD (2002) Fracture behavior in a pressure vessel steel weld. Mater Des 23:371–376
3. Jang YC, Hong JK, Park JH, Kim DW, Lee Y (2008) Effects of notch position of the Charpy impact specimen on the failure behavior in heat affected zone. J Mater Process Technol 201:419–424
4. Kim JH, Yoon EP (1998) Notch position in the HAZ specimen of reactor pressure vessel steel. J Nucl Mater 257:303–308
5. Kameda J, Takahashi H, Suzuki M (1978) Residual stress relief and local embrittlement in a A533B reactor pressure vessel weldment. Int J Press Vessels Piping 6:245–274
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