Effect of heat treatments on tensile properties of F82H steel irradiated by neutrons

Wakai, Eiichi; Ando, Masami; Sawai, Tetsuo; Tanigawa, Hiroyasu; Taguchi, Taketoshi; Stoller, R.E.; Yamamoto, Toshio; Kato, Yoshiaki; Takada, Fumiki

doi:10.1016/j.jnucmat.2007.03.164

Cited by 12 publications

(10 citation statements)

References 19 publications

(18 reference statements)

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“…In agreement with in literature data on [4,5] the influence of the difference of tempering conditions on proof stress before and after irradiation, the increment of the proof stress (DYS) depends on …”

Section: Influence Of Heat Treatment History On Irradiation-responsesupporting

confidence: 91%

“…5 shows the tensile properties in the plate region (II) and cooling channel region (III) of the mock-up before and after irradiation. For the sake of comparison, the tensile properties of an IEA-F82H steel are also given (I) [3][4][5]. Irradiation and test temperatures are 523 K. The 0.2% proof stresses are given in (a) of the figure, the total elongations in (b), and the uniform elongations in (c).…”

Section: Influence Of Heat Treatment History On Irradiation-responsementioning

confidence: 99%

“…Changes of strength and elongation in I: IEA-F82H steel[3][4][5], II: matrix region of plate and III: matrix region of channel, irradiated and tested at about 523 K.…”

mentioning

confidence: 99%

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Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Furuya

Wakai

Miyamoto

et al. 2007

Journal of Nuclear Materials

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Section: Influence Of Heat Treatment History On Irradiation-responsesupporting

confidence: 91%

Section: Influence Of Heat Treatment History On Irradiation-responsementioning

confidence: 99%

See 1 more Smart Citation

Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Furuya

Wakai

Miyamoto

et al. 2007

Journal of Nuclear Materials

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“…Major mechanical and physical properties, such as tensile, toughness, fatigue properties, thermal conductivities, magnetic properties, etc. of base metal and welds, were measured and reported [8,19,20], and the effect of various heat treatments was also reported [21]. Long-term tests, such as creep-rupture tests and aging tests up to 100K h, were also conducted [22][23][24].…”

Section: Databasementioning

confidence: 99%

Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

Tanigawa¹,

Hirose²,

Shiba³

et al. 2008

Fusion Engineering and Design

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“…experiments and modeling on the basic underlying physical mechanisms [9][10][11][12][13][14][15][16][17][18][19][20][21][22][23]. For example, it is well established that the effect of irradiation on ferritic-martensitic alloys at low to intermediate temperatures is increased yield stress, reduced strain hardening capacity, and flow localization at lower strains [24][25].…”

Section: Introductionmentioning

confidence: 99%

Large Scale DD Simulation Results for Crystal Plasticity Parameters in Fe-Cr And Fe-Ni Systems

Zbib¹,

Li²,

Sun³

et al. 2012

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SUMMARYThe development of viable nuclear energy source depends on ensuring structural materials integrity. Structural materials in nuclear reactors will operate in harsh radiation conditions coupled with high level hydrogen and helium production, as well as formation of high density of point defects and defect clusters, and thus will experience severe degradation of mechanical properties. Therefore, the main objective of this work is to develop a capability that predicts aging behavior and in-service lifetime of nuclear reactor components and, thus provide an instrumental tool for tailoring materials design and development for application in future nuclear reactor technologies. Towards this end goal, the long term effort is to develop a physics-based multiscale modeling hierarchy, validated and verified, to address outstanding questions regarding the effects of irradiation on materials microstructure and mechanical properties during extended service in the fission and fusion environments. The focus of the current investigation is on modern steels for use in nuclear reactors including high strength ferritic-martensitic steels (Fe-Cr-Ni alloys).The effort is to develop a predictive capability for the influence of irradiation on mechanical behavior. Irradiation hardening is related to structural information crossing different length scales, such as composition, dislocation, and crystal orientation distribution. To predict effective hardening, the influence factors along different length scales should be considered. Therefore, a hierarchical upscaling methodology is implemented in this work in which relevant information is passed between models at three scales, namely, from molecular dynamics to dislocation dynamics to dislocation-based crystal plasticity. The molecular dynamics (MD) was used to predict the dislocation mobility in body centered cubic (bcc) Fe and its Ni and Cr alloys. The results are then passed on to dislocation dynamics to predict the critical resolved shear stress (CRSS) from the evolution of local dislocation and defects.In this report the focus is on the results obtained from large scale dislocation dynamics simulations. The effects of defect density and materials structure were investigated while new evolution laws were proposed. These results will form the bases for the development of evolution and hardening laws for a dislocation-based crystal plasticity framework. The hierarchical upscaling method being developed in this project can provide a guidance tool to evaluate performance of structural materials for nextgeneration nuclear reactors. Combined with other tools developed in the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the models developed will have more impact in improving the reliability of current reactors and affordability of new reactors.

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Effect of heat treatments on tensile properties of F82H steel irradiated by neutrons

Cited by 12 publications

References 19 publications

Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Effects of irradiation on mechanical properties of HIP-bonded reduced-activation ferritic/martensitic steel F82H first wall

Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

Large Scale DD Simulation Results for Crystal Plasticity Parameters in Fe-Cr And Fe-Ni Systems

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