Embrittlement behaviour of different international low activation alloys after neutron irradiation

Rieth, M.; Dafferner, B.; Röhrig, Horst

doi:10.1016/s0022-3115(98)00171-8

Cited by 82 publications

(65 citation statements)

References 5 publications

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“…Therefore, the effects of neutron irradiation on tensile deformation, ductile to brittle transition temperature (DBTT), and microstructures of F82H and the other ferritic/martensitic steels have been extensively investigated. [1][2][3][4][5][6][7][8][9][10][11][12][13] On the course of these research activities, hardening and upward shift of DBTT induced by neutron bombardment have been commonly regarded as crucial problems. Radiation hardening occurs mainly at irradiation temperatures lower than about 400 C, and it increased with decreasing irradiation temperature down to about 250 C. The DBTT tends to increase with decreasing irradiation temperature as well, and the shift increases largely at 250 C. The issue of helium accumulation effects on these properties has been an ongoing concern.…”

Section: Introductionmentioning

confidence: 99%

“…The studies on DBTT shift due to helium have been done by several researchers. [8][9][10] However, the details of the dependence of DBTT on helium production has not been made clear yet. Radiation-induced degradation of fracture toughness related to helium production is recognized to be one of the critical issues of the alloys.…”

Section: Introductionmentioning

confidence: 99%

“…One of purpose in this study is to evaluate quantitatively the contribution of helium production to radiation hardening in F82H as a function of irradiation temperature and helium concentration, considering the synergistic effect of helium and displacement damage by means of 10 B-method. Several researchers 6,[8][9][10][32][33][34] reported that the increase of yield strength and the shift of DBTT were different in several martensitic steels, such as F82H, JLF-1, JLF-1B, ORNL 9Cr-2WVTa, OPTIFER Ia, II, MANET II and Mod.9Cr-1Mo, which had different concentrations in some elements and were tempered at different temperatures. The effects of the normalizing and tempering of heat treatment on tensile and impact behavior in martensitic steels before irradiation were reported by Schafer and Gondi.…”

Section: Introductionmentioning

confidence: 99%

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Effects of Helium Production and Heat Treatment on Neutron Irradiation Hardening of F82H Steels Irradiated with Neutrons

Wakai¹,

Taguchi²,

Yamamoto³

et al. 2005

Mater. Trans.

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The influcence of addition of 10 B and 11 B on radiation hardening as a function of irradiation temperature was examined in reducedactivation martensitic F82H+B steels (8Cr-2W-0.2V-0.04Ta-0.1C-0.006B). Specimens used were 10 B doped, 10 B+ 11 B doped and 11 B doped F82H steels. Helium concentration produced in the specimens through 10 B(n, ) 7 Li reaction was measured from about 15 to about 330 appm. Radiation hardening of the specimens irradiated at 300 C to 2.3 dpa and 150 C to 1.9 dpa was observed. Increment of radiation hardening possibly due to helium in the specimen irradiated at 300 C tended to increase slightly with increasing helium production in tensile test at 20 C, but it was not observed for 150 C irradiation. Therefore, it can be mentioned that the enhancement of radiation hardening in the 10 B( 11 B) doped steels depends on irradiation temperature. The dependence of radiation hardening on tempering time was also examined for F82H-std irradiated at 150 C to 1.9 dpa. Increment of yield strength of F82H-std tended to increase with increasing tempering time. The relation between the shift of DBTT and the increment of yield strength due to irradiation suggest that the extension of tempering time or the increase of tempering temperature would be beneficial for mechanical properties of F82H-std.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Effects of Helium Production and Heat Treatment on Neutron Irradiation Hardening of F82H Steels Irradiated with Neutrons

Wakai¹,

Taguchi²,

Yamamoto³

et al. 2005

Mater. Trans.

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“…The effects of neutron irradiation on tensile deformation, DBTT, and microstructures of F82H and the other ferritic/martensitic steels were reported. [1][2][3][4][5][6] Radiation hardening occurred mainly at irradiation temperatures lower than about 400 C, and it increased with decreasing irradiation temperature up to about 250 C. The issue of helium accumulation on mechanical properties has been an ongoing concern. Recently, the effect of helium production on radiation hardening has been examining and the large enhancement of hardening due to helium from 600 appm to 10000 appm is detected in the tensile testing for 9Cr martensitic steels EM10 and T91 implanted by cyclotron experiments.…”

Section: Introductionmentioning

confidence: 99%

Mechanical Property of F82H Steel Doped with Boron and Nitrogen

Wakai¹,

Matsukawa²,

Yamamoto³

et al. 2004

Mater. Trans.

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Dependence of fracture properties and hardening was examined as a function of helium production in tensile specimens of a martensitic steel F82H (Fe-8Cr-2W-0.1C-0.04Ta) irradiated at 300 C to 2.3 dpa by neutron irradiation in the JMTR (Japan Materials Testing Reactor). The specimens used in this study were F82H, F82H+60 ppm 11 B, F82H+30 ppm ( 11 B+ 10 B) and F82H+60 ppm 10 B. The helium range produced from 10 B (n,) 7 Li reaction was from 5 to 330 appm in the specimens. The tensile testing was performed at 25 C. The radiation hardening due to helium production was detected at 330 appmHe. The degradation of fracture stress due to helium production was approximately evaluated from the fracture strength and the reduction area. Effect of specimen size on tensile and Charpy impact properties in F82H doped with 60 ppm boron and 200 ppm nitrogen was also examined. The JIS 14A and SS-J3 (Small Size-Japanese-3 type) were used for the tensile specimens, and half size (55 mm in length, 10 mm in height and 5 mm in width) and 0.5-1/3CVN (18 mm in length, 3.3 mm in height and 1.65 mm in width) were used for the Charpy impact testing. The tensile properties were a similar to each other. However, the ductile-brittle transition temperature measured in smaller size specimen was somewhat lower than that in the standard size specimen.

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“…F82H and 9Cr2WVTa (ORNL Ht. 3791), show a much lower shift of DBTT after irradiation to several dpa with neutrons [2,3]. For this reason, the lowactivation martensitic steels have been included in irradiation programs oriented for spallation targets [4,5].…”

Section: Introductionmentioning

confidence: 99%

Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiation

Dai

Maloy

Bauer

et al. 2000

Journal of Nuclear Materials

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Low-activation martensitic steels, F82H (mod.) and Optimax-A, have been irradiated with 800-MeV protons up to 5.9 dpa. The tensile properties and microstructure have been studied. The results show that radiation hardening increases continuously with irradiation dose. F82H has lesser irradiation hardening as compared to Optimax-A in the present work and DIN1.4926 from a previous study. The irradiation embrittlement eects are evident in the materials since the uniform elongation is reduced sharply to less than 2%. However, all the irradiated samples ruptured in a ductile-fracture mode. Defect clusters have been observed. The size and the density of defect clusters increase with the irradiation dose. Precipitates are amorphous after irradiation. Ó

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Embrittlement behaviour of different international low activation alloys after neutron irradiation

Cited by 82 publications

References 5 publications

Effects of Helium Production and Heat Treatment on Neutron Irradiation Hardening of F82H Steels Irradiated with Neutrons

Effects of Helium Production and Heat Treatment on Neutron Irradiation Hardening of F82H Steels Irradiated with Neutrons

Mechanical Property of F82H Steel Doped with Boron and Nitrogen

Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiation

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