ODS cladding fuel pins irradiation tests using the BOR-60 reactor

Kaito, Takeji; Yano, Yasuhide; Ohtsuka, Satoshi; Inoue, Masakí; Tanaka, Kenya; Fedoseev, A.; Povstyanko, A.V.; Novoselov, A. E.

doi:10.1080/00223131.2013.773165

Cited by 17 publications

(18 citation statements)

References 15 publications

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“…3,4) The largest size of the coarse and irregular precipitates was roughly 40 µm at first glance; however, the magnified view revealed that the coarse and irregular precipitates were actually aggregates consisting of relatively small precipitates. The image analysis indicated that the largest equivalent diameter was 22 µm as seen in Fig.…”

Section: Resultsmentioning

confidence: 99%

“…3,4) In this irradiation test, coarse and irregular precipitates were formed in the high-temperature region of the cladding tube. 3,4) This microstructure change was quite anomalous, and had never been reported before in research studies on irradiation and thermal responses of ferritic steels including ODS steels. An investigation to determine the cause of this anomalous microstructure change was previously carried out, and the 9Cr-ODS steel tube used for the BOR-60 irradiation test was found to contain metallic Cr inclusions.…”

Section: Introductionmentioning

confidence: 99%

“…The cause was determined to be the combined effects of the heterogeneity of the matrix Cr composition (presence of metallic Cr inclusions) and the high-temperature environment in the BOR-60 irradiation test. 3,4) In this study, the high-temperature thermal aging tests of pre-mix process 9Cr-ODS steels were carried out to reproduce the anomalous microstructure change that occurred in the BOR-60 irradiation test specimens. The mechanism producing this microstructure change was discussed.…”

Section: Introductionmentioning

confidence: 99%

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Microstructure Characterization of Oxide Dispersion Strengthened Steels Containing Metallic Chromium Inclusions after High-Temperature Thermal Aging

et al. 2013

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Microstructure characterizations of 9Cr-oxide dispersion strengthened (ODS) steels were carried out after high-temperature thermal aging to reproduce the anomalous microstructure change that occurred in the BOR-60 irradiation test ® formation of abnormally coarse and irregular precipitates a few tens of micrometers in size. The 750°C thermal aging for 8,000 h produced the precipitate growth in normalized-and-tempered (NTed) 9Cr-ODS steels, however, the largest precipitates were only a few micrometers. The furnace-cooling (FC) heat treatment produced the matrix structure change from tempered martensite to ¡-ferrite, but the precipitate size after the thermal aging was in the same level as that in the NTed 9Cr-ODS steel. In the case of NTed defective 9Cr-ODS steel containing metallic Cr inclusions, coarse and irregular precipitates were formed nearby metallic Cr inclusions after the 750°C thermal aging for 8,000 h. In the case of FCed defective 9Cr-ODS steel containing metallic Cr inclusions, the 750°C thermal aging for 8,000 h produced the pronounced growth of coarse and irregular precipitates, which was equivalent to the anomalous microstructure change in the BOR-60 irradiation test. Based on the analyses using energy dispersive X-ray spectrometry (EDX) and electron backscattered pattern (EBSP), coarse and irregular precipitates were identified as M23C6.

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Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Microstructure Characterization of Oxide Dispersion Strengthened Steels Containing Metallic Chromium Inclusions after High-Temperature Thermal Aging

et al. 2013

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“…One of the experimental fuel assemblies (EFAs), VS424E, containing 9Cr-ODS steel cladding fuel pins achieved the best data, i.e., peak burn-up of 11.9at% and peak neutron dose to 51 dpa [6]. However, in another EFA, VS423E, which achieved a lower burn-up (10.5at% at peak) and lower neutron dose (44 dpa at peak) than VS424E, one of the 9Cr-ODS steel cladding fuel pins failed [6]. The microstructure in the vicinity of the ruptured area was quite peculiar and has never been reported before.…”

Section: Introductionmentioning

confidence: 99%

“…Four EFAs containing 9Cr-ODS steel cladding fuel pins were previously irradiated in the BOR-60 to demonstrate the in-reactor performance of 9Cr-ODS steel used for fuel cladding tubes [6][7][8]. The EFA in the third irradiation test, VS424E, achieved the maximum peak burnup of 11.9at% and neutron dose of 51 dpa, without any microstructure instability or any fuel pin rupture.…”

Section: Outline Of Bor-60 Fuel Pin Irradiation Tests [6-8]mentioning

confidence: 99%

Investigation of the cause of peculiar irradiation behavior of 9Cr-ODS steel in BOR-60 irradiation tests

Ohtsuka

Kaito

Yano

et al. 2013

Journal of Nuclear Science and Technology

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Four experimental fuel assemblies (EFAs) containing 9Cr-ODS steel cladding fuel pins were previously irradiated in the BOR-60 to demonstrate the in-reactor performance of 9Cr-ODS steel for use as fuel cladding tubes. One of the EFAs achieved the best data, a peak burn-up of 11.9at% and a neutron dose of 51 dpa, without any microstructure instability or any fuel pin rupture. On the other hand, in another EFA (peak burn-up, 10.5at%; peak neutron dose, 44 dpa), peculiar irradiation behaviors, such as microstructure instability and fuel pin rupture, occurred. Investigations of the cause of these peculiar irradiation behaviors were carried out. The detection sensitivity in an ultrasonic inspection test was shown to be low for the metallic Cr and metallic Fe inclusions. The peculiar microstructure change reappeared with high-temperature thermal-aging of the 9Cr-ODS steel containing metallic Cr inclusions. The strength and ductility of the defective part containing metallic Cr inclusions were appreciably lower than those of a standard part without the inclusions. The combined effects of matrix Cr heterogeneity (presence of metallic Cr inclusions) and high-temperature irradiation were concluded to be the main cause of the peculiar microstructure change in 9Cr-ODS steel cladding tubes in the BOR-60 irradiation tests. They contributed to the fuel pin rupture.

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Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure

Sornin

Ehrnstén

Mozzani³

et al. 2021

Metall Mater Trans A

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9Cr and 14Cr ODS steel tubes are creep tested by inner gas pressure representative of the fission gas loading encountered in service conditions. • Creeps tests handled by 4 different European teams with different experimental set-up are consistent showing a very low scattering • The ODS steel tubes typical failure mode is leakage without burst on a longitudinal crack occurring at very low hoop strain.

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ODS cladding fuel pins irradiation tests using the BOR-60 reactor

Cited by 17 publications

References 15 publications

Microstructure Characterization of Oxide Dispersion Strengthened Steels Containing Metallic Chromium Inclusions after High-Temperature Thermal Aging

Microstructure Characterization of Oxide Dispersion Strengthened Steels Containing Metallic Chromium Inclusions after High-Temperature Thermal Aging

Investigation of the cause of peculiar irradiation behavior of 9Cr-ODS steel in BOR-60 irradiation tests

Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure

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