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Evaluation of Transition Temperature in Reactor Pressure Vessel Steels 6using the Fracture Energy Transition Curve from a Small Punch Test

机译：反应堆压力容器钢的转变温度评价6用小冲击试验中的断裂能量转变曲线

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Tae-kyung Lee; Seokmin Hong; Jongmin Kim; Min-Chul Kim; Jae-il Jang;
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1. Fracture Toughness Evaluation of a Low Toughness Weldment of Reactor Pressure Vessel Steel by Ball Indentation Tests in the Transition Region [J] . H.S.Cho, W.J.Yang Journal of Korean Institute of Metal and Materials . 2000,第9期

机译：过渡区球压痕试验评价反应堆压力容器钢低韧性焊缝的断裂韧性
2. Application of the local fracture stress model on the cleavage fracture of the reactor pressure vessel steels in the transition temperature region [J] . Yang WJ., Lee BS., Huh MY., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2003,第2a3期

机译：局部断裂应力模型在转变温度区反应堆压力容器钢解理断裂中的应用
3. Correlation between Cleavage Fracture Toughness and Charpy Impact Properties in the Transition Temperature Range of Reactor Pressure Vessel Steels [J] . Kunio ONIZAWA, Masahide SUZUKI JSME International Journal. Series C, Mechanical Systems, Machine Elements and Manufacturing . 2004,第3期

机译：反应堆压力容器钢转变温度范围内劈裂韧性与夏比冲击性能的相关性
4. THE FRACTURE TOUGHNESS PROPERTIES OF CHINA MANUFACTURED REACTOR PRESSURE VESSEL STEELS IN TRANSITION TEMPERATURE RANGE [C] . Kai Sun, Xiaoyong Wu, Guoyun Li, ASME Pressure Vessels and Piping Conference . 2019

机译：中国制造的反应堆压力容器钢的断裂韧性特性在过渡温度范围内
5. The development of a curved centre cracked specimen for fracture toughness testing of CANDU reactor pressure tubes. [D] . Wallace, A.C. 1988

机译：弯曲中心裂纹试样的开发，用于测试CANDU反应堆压力管的断裂韧性。
6. On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels [O] . N. Almirall, P. B. Wells, H. Ke, -1

机译：高辐照反应堆压力容器钢中较低温度下形成的纳米Mn-Ni-Si沉淀物的高温热稳定性研究
7. Fracture Toughness Evaluation of Japanese Reactor pressure Vessel Steels Using Master Curve Approach(Maintenance Inspection and Monitoring,Power and Energy System Symposium) [O] . Naoki MIURA, Naoki SONEDA 2009

机译：日本反应器压力容器钢的断裂韧性评价母曲线方法（维护检验和监测，<特刊>电力和能源系统研讨会）
8. Investigation into the Dependence of the Brittle Fracture Transition Temperature Shift on the Irradiation Temperature for Some Reactor Pressure Vessel Steels with Different Copper Content. [R] . Ahlf, J., Schmitt, F. J. 1982

机译：不同铜含量反应堆压力容器钢脆性断裂转变温度变化对辐照温度的影响。

Evaluation of Transition Temperature in Reactor Pressure Vessel Steels 6using the Fracture Energy Transition Curve from a Small Punch Test

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