共 9 条
- [1] Boiler and pressure vessel code: section II, pp. 258-266, (2004)
- [2] Rules for inservice inspection of nuclear power plant components: boiler and pressure vessel code: section XI, pp. 392-402, (2004)
- [3] Rosinskin S.T., Server W.L., Application of the master curve in the ASME code, Pressure Vessels and Piping, 77, pp. 59-598, (2000)
- [4] Radiation embrittle- ment of reactor vessel materials: NRC-RG1.99-Rev. 2, pp. 1-10, (1988)
- [5] Standard test method for determination of reference temperature T<sub>0</sub> for ferritic steels in the transition range: ASTM E1921-11, pp. 1-23, (2011)
- [6] Use of fracture toughness test data to establish reference temperature for pressure retaining materials for Section XI: ASME code case N-629, pp. 1-15, (1999)
- [7] US Nuclear Regulatory Commission.Fracture toughness requirements: rules and regulations title 10 code of federal regulations part 50 appendix G, pp. 1-13, (1986)
- [8] Mark K., Randy L., Initial reference temperatures and irradiation trend curves for use with RTT0, a preliminary assessment, Pressure Vessels and Piping, 393, 3, pp. 71-78, (1999)
- [9] Randy L., Mark K., Charlie K., Application of master curve technology to estimation of end of license adjusted reference temperature for a nuclear power plant, Pressure Vessels and Piping, 393, 2, pp. 79-89, (1999)