Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures

Rowcliffe, A.F.; Robertson, J.P.; Klueh, R.L.; Shiba, K.; Alexander, David; Grossbeck, M.L.; Jitsukawa, Shiro

doi:10.1016/s0022-3115(98)00163-9

Cited by 66 publications

(32 citation statements)

References 4 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%

“…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%

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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“…However for extending the operating life time of these reactors, extensive R&D to investigate corrosion and neutroninduced material degradation phenomena is in progress. Fracture toughness data collected for Types 304 and 316 austenitic stainless steels in LWR conditions of 523-623 K clearly showed fracture toughness while approaching value near 50 MPa m 1/2 after 5-10 dpa (Pawel et al, 1996;Rowcliffe et al, 1998). Intensive investigations are completed on the possibility of neutron radiation-induced embrittlement of reactor pressure vessels (Odette and Nanstad, 2009).…”

Section: Materials Degradation In Water Reactor Systemsmentioning

confidence: 99%

Materials Science & Technology: Research and Challenges in Nuclear Fission Power

Raja¹

2015

Proceedings of the Indian National Science Academy

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The performance and integrity of structural and functional materials are key issues in the safety and competitiveness of current and future nuclear fission reactors being developed for sustainable nuclear energy applications. The challenges towards development of nuclear structural materials arise due to the demanding hostile environments with respect to radiation, temperature, stress, etc., and requirements of total reliability and high performance over the long service life (say 60 years). A successful materials science research programme in nuclear industry has to take into account these challenges to improve the performance of materials and components in the emerging scenario of extending life of existing plants and realizing advanced reactors. In this study, material challenges associated with water reactors and fast breeder reactors (FBR) with focus on short-term and long-term strategies for materials development are considered. The materials in the existing and proposed future nuclear fission reactors are summarized along with a description of major material degradation mechanisms in different environments. The priority in the nuclear industry is to extend the life of reactors with robust safety features and sufficient cost-effectiveness, beyond forty to sixty years and from sixty to even one hundred years. The importance of modelling and developing predictive tools to estimate materials behaviour for effective computing of lifetime of nuclear reactor components is fast developing to cut down cost and time and also to enhance safety and confidence in existing and new systems. The future FBR technology relies heavily on advanced waste management and effective proliferation resistance. We review advanced reactor concepts of Generation IV forum and the new materials and technologies. Nuclear energy is not the right option for every country. Careful examination of the energy basket and commitment over a long period with effective mechanisms of safety governance is the key to make a decision to harness large amounts of nuclear energy. China, France, India, Russia, USA,UK, etc. are extremely committed to use large amounts of nuclear energy. Japan after the Fukushima accident, faces a challenge of public acceptance though the country has deep and rich expertise in nuclear technology and it is advantageous to produce low carbon power, on a sustained competitive basis from nuclear energy.

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Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures

Cited by 66 publications

References 4 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

Materials Science & Technology: Research and Challenges in Nuclear Fission Power

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