Research Progress of Steels for Nuclear Reactor Pressure Vessels

Abstract

The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel. Based on the characteristics of large size and wall thickness of the nuclear pressure vessel, combined with its performance requirements, this work studies the problems of forging technology, mechanical properties, irradiation damage, corrosion failure, thermal aging behavior and fatigue properties, and summarizes the research progress of nuclear pressure vessel materials. The influencing factors of microstructures evolution and mechanism of mechanical properties change of nuclear pressure vessel steel are analyzed in this work. The mechanical properties before and after irradiation are compared, and the influence mechanisms of irradiation hardening and embrittlement are also summarized. Although the stainless steel will be surfacing on the inner wall of nuclear pressure vessel to prevent corrosion, long-term operation may cause aging or deterioration of stainless steel, resulting in corrosion caused by the contact between the primary circuit water environment and the nuclear pressure vessel steel. Therefore, the corrosion behavior of nuclear pressure vessels materials is also summarized in detail. Meanwhile, the evolution mechanism of the microstructure of nuclear pressure vessel materials under thermal aging conditions is analyzed, and the mechanisms affecting the mechanical properties are also described. In addition, the influence mechanisms of internal and external factors on the fatigue properties, fatigue crack initiation and fatigue crack propagation of nuclear pressure vessel steel are analyzed in detail from different perspectives. Finally, the development direction and further research contents of nuclear pressure vessel materials are prospected in order to improve the service life and ensure safe service in harsh environment.

Sustainable New Technology for the Improvement of Metallic Materials for Future Energy Applications

“…Low-alloyed steel (Ferritic steels: A105 [169], A106 GrB [31], A182 [169], A216 GrWCB [31], A302 GrB [169,170], A333 Gr6 [31], SA212 B [169]; A508 Gr3 [169,[171][172][173][174], A516 Gr70 [31], A533 A [31], A555 B [31], 15Kh2NMFA [175,176], 08Kh18N10T [177]; bainitic steels: 1Cr1Mo0.25v [31], 2Cr1MoGr 22 [31], NiCrMoV [31]; duplex steel: 2507 [159], DSS [178], Fe20Cr9Ni [179]; carbon steel: AISI 1018 [159])…”

Effect of Thermal Aging on the Microstructure and Mechanical Properties of ER308L/Z2CND18.12N2 Dissimilar Welds

“…On the other hand, the microstructure evolutions, spinodal decomposition, and Gphase precipitation lead to the embrittlement of the ferrite phase after long thermal aging [8,[33][34][35]. Although the literature has proved that microhardness has a linear relation with the variations in ferrite decomposition after thermal aging in ER308L [21,36] and Z2CN18.12N2 [37,38], few reports are concerned with the effect of thermal aging on the microstructure of FZ in DMWJs.…”

Tailoring Low‐Alloyed Cryogenic Steel Strong and Tough Introduces Fine‐Grained Equiaxed Ferrite by Intercritical Subquenching

“…As a result, the criteria for cryogenic vessel steels have become increasingly stringent. [1][2][3] The choice of steel for cryogenic vessels necessitates high strength, high ductility, and exceptional low-temperature toughness. [4,5] To date, the most extensively studied cryogenic vessel material is nickel steel.…”