Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II

Garner, F.А.; Makenas, B.J.; Chastain, S.A.

doi:10.1016/j.jnucmat.2011.03.055

Cited by 12 publications

(4 citation statements)

References 34 publications

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“…With the exception of test specimens irradiated in various reactors such as BOR-60 [7], Phénix and OSIRIS [8], and BR-2 [9], most of the insight on r adiation damage in this steel has been generated using data derived from examination of structural components and test specimens irradiated in EBR-II [10][11][12][13][14][15][16][17][18][19][20]. For many years, the focus of these studies was primarily on void swelling and irradiation creep, and secondarily on pha se instabilities, which are not as pronounced in 304 stainless steel compared to other austenitic steels such as AISI 316.…”

Section: Introductionmentioning

confidence: 99%

Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Dong

Sencer

Garner³

et al. 2015

Journal of Nuclear Materials

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AISI 304 stainless steel was irradiated at 416°C and 450 o C at a 4.4x10-9 and 3.05×10-7 dpa/s to ~0.4 and ~28 dpa, respectively, in the reflector of the EBR-II fast reactor. Both unirradiated and irradiated conditions were examined using standard and scanning transmission electron microscopy, energy dispersive spectroscopy, and atom probe tomography on very small specimens produced by the focused ion beam milling. These results are compared with previous electron microscopy examination of 3 mm disks from essentially the same material. By comparing a very low dose specimen with a much higher dose specimen, both derived from a single reactor assembly, it has been demonstrated that the coupled microstructural and microchemical evolution of dislocation loops and other sinks begins very early, with elemental segregation producing at these sinks what appears to be measurable precursors to fully formed precipitates found at higher doses. The nature of these sinks and their possible precursors are examined in detail.

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Section: Introductionmentioning

confidence: 99%

Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Dong

Sencer

Garner³

et al. 2015

Journal of Nuclear Materials

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“…Using accelerator irradiations with Cr 3+ and Ar + ions allowed studying effects of dose rate, different initial structure state and implanted ions on features of structure evolution and main mechanisms of degradation including low temperature swelling and embrittlement of the 18Cr10NiTi steel [25,26]. It was shown that differences in dose rate at most irradiation temperatures mainly exert their influence on the duration of the swelling transient regime.…”

Section: Materials Of Pressure Vessel Internalsmentioning

confidence: 99%

Mechanisms of Radiation Damage and Development of Structural Materials for Operating and Advanced Nuclear Reactors

Voyevodin¹,

Tolstolutskaya²,

Tikhonovsky³

et al. 2021

Problems of Atomic Science and Technology

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Safety of nuclear reactor (NR) and economic of nuclear power are determined to high degree by structural materials. Study of reasons of change of physical-mechanical properties of materials and of their dimensional stability under irradiation; determination of operation life of elements of nuclear power energetic assemblies in different conditions, selection and development of prospective materials with high radiation resistance are the main objectives of radiation material science. In the presented paper, mechanisms of radiation damage of structural materials for nuclear power and problems of development of radiation-resistant materials for operating and advanced NR of new generation are examined.

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“…Garner et al [ 10 ] studied swelling and creep phenomena irradiated in EBR-II. They illustrated how the swelling reached high levels rather quickly by reducing both fuel pin cladding interaction and the contribution of the irradiation to the total deformation.…”

Section: Introductionmentioning

confidence: 99%

Stability Improvement of Flexible Shallow Shells Using Neutron Radiation

et al. 2020

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Microelectromechanical systems (MEMS) are increasingly playing a significant role in the aviation industry and space exploration. Moreover, there is a need to study the neutron radiation effect on the MEMS structural members and the MEMS devices reliability in general. Experiments with MEMS structural members showed changes in their operation after exposure to neutron radiation. In this study, the neutron irradiation effect on the flexible MEMS resonators’ stability in the form of shallow rectangular shells is investigated. The theory of flexible rectangular shallow shells under the influence of both neutron irradiation and temperature field is developed. It consists of three components. First, the theory of flexible rectangular shallow shells under neutron radiation in temperature field was considered based on the Kirchhoff hypothesis and energetic Hamilton principle. Second, the theory of plasticity relaxation and cyclic loading were taken into account. Third, the Birger method of variable parameters was employed. The derived mathematical model was solved using both the finite difference method and the Bubnov–Galerkin method of higher approximations. It was established based on a few numeric examples that the irradiation direction of the MEMS structural members significantly affects the magnitude and shape of the plastic deformations’ distribution, as well as the forces magnitude in the shell middle surface, although qualitatively with the same deflection the diagrams of the main investigated functions were similar.

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Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II

Cited by 12 publications

References 34 publications

Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Mechanisms of Radiation Damage and Development of Structural Materials for Operating and Advanced Nuclear Reactors

Stability Improvement of Flexible Shallow Shells Using Neutron Radiation

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