Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals

Bruemmer, S.M.; Simonen, E.P.; Scott, Peter; Andresen, Peter L.; Was, Gary S.; Nelson, J.L.

doi:10.1016/s0022-3115(99)00075-6

Cited by 346 publications

(196 citation statements)

References 32 publications

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“…In austenitic stainless steels, which are used as core materials for the boiling water reactor (BWR) and pressurized water reactor (PWR), radiation-induced segregation (RIS) near the grain boundaries degrades their mechanical and chemical properties significantly [4][5][6][7]. The gravity of this problem has been considered as irradiation-assisted stress corrosion cracking (IASCC) caused by the RIS because of the depletion of the chromium concentration near the grain boundaries [8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

Sakaguchi¹,

Endo²,

Watanabe³

et al. 2013

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

Sakaguchi¹,

Endo²,

Watanabe³

et al. 2013

Journal of Nuclear Materials

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“…Over the past decade, there have been significant advances in the understanding of degradation mechanisms in austenitic stainless steel reactor internals as summarized in several review papers [1,2]. Based substantially on this advance in knowledge, efforts to develop austenitic stainless steel structural materials with enhanced radiation resistance have been undertaken.…”

Section: Introductionmentioning

confidence: 99%

The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

Cole

Allen

Was

et al. 2004

Effects of Radiation on Materials: 21st International Symposium

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Abstract:The effect of pre-irradiation heat treatments on thermal non-equilibrium grain boundary segregation (TNES) and subsequent radiation-induced grain boundary segregation (RIS) is studied in a series of model austenitic stainless steels. The alloys used for this study are based on AISI 316 stainless steel and have the following nominal compositions: Fe-16Cr-13Ni-1.25Mn (base 316), Fe-16Cr-13Ni-1.25Mn-2.0Mo (316 + Mo) and Fe-16Cr-13Ni-1.25Mn-2.0Mo-0.07P (316 + Mo + P). Samples were heat treated at temperatures ranging from 1100 to 1300°C and cooled at 4 different rates (salt brine quench, water quench, air cool and furnace cool) to evaluate the effect of annealing temperature and quench rate on TNES. The alloys were than processed with the treatment (temperature and cooling rate) that resulted in the maximum Cr enrichment. Alloys with and without the heat treatment to enrich the grain boundaries with Cr were characterized following irradiation to 1 dpa at 400°C with high-energy protons in order to understand the influence of alloying additions and pre-irradiation grain boundary chemistry on irradiation-induced elemental enrichment and depletion profiles. Various mechanistic models will be examined to explain the observed behavior.

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“…5 shows atomic maps of the elements in the APT specimen. The volume of the needle was measured to be 114×115×205 nm 3 , and about 10 million atoms were collected and reconstructed. Because of the large number of atoms, the enrichment of Ni and depletion of Cr were not evident in Fig.…”

Section: Methodsmentioning

confidence: 99%

“…Neutron irradiation leads to RIS in SS during service-corresponding to the depletion of Cr and the enrichment of Ni, Si, and P at defect sinks. The depletion of Cr might enhance irradiation-assisted stress corrosion cracking of SS, and this might reduce the integrity of nuclear power plants, especially in case of boiling water reactors [2][3]. Thus, numerous studies on RIS in SS and model alloys have been performed over the three last decades [4][5][6][7][8][9][10][11][12][13].…”

Section: Introductionmentioning

confidence: 99%

Atomistic Analysis Of Radiation-Induced Segregation In Ion-Irradiated Stainless Steel 316

Lee¹,

Jin²,

Chang³

et al. 2015

Archives of Metallurgy and Materials

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Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is known that these alloys exhibit radiation-induced segregation (RIS) at point defect sinks at moderate temperature, while in service. The RIS behavior of SS can be a potential problem by increasing the susceptibility to irradiation-assisted stress corrosion cracking. In this work, the RIS behavior of solute atoms at sinks in SS 316 irradiated with Fe 4+ ions were characterized by atom probe tomography (APT). There were torus-shaped defects along with a depletion of Cr and enrichment of Ni and Si. These clusters are believed to be dislocation loops resulting from irradiation. The segregation of solutes was also observed for various defect shapes. These observations are consistent with other APT results from the literature. The composition of the clusters was analyzed quantitatively almost at the atomic scale. Despite the limitations of the experiments, the APT analysis was well suited for discovering the structure of irradiation defects and performing a quantitative analysis of RIS in irradiated specimens.

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Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals

Cited by 346 publications

References 32 publications

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys

Atomistic Analysis Of Radiation-Induced Segregation In Ion-Irradiated Stainless Steel 316

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