Swellling of advanced austenitic stainless steels developed for the environment of heavy neutron exposure

Shibahara, I.; Akasaka, Naoaki; Onose, Shoji; Okada, Hideya; Ukai, Shigeharu

doi:10.1016/0022-3115(94)90109-0

Cited by 25 publications

(8 citation statements)

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“…Облучение образцов нейтронами проводили в реакторе ИВВ-2М при 77-300 K в ин-тервале флюенсов (1,(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15) Измерения остаточного электросопротивления (при 4,2 К) выполнялись с исполь-зованием стандартного четырехконтактного метода с чувствительностью на уровне 0,01 нОм•см и точностью 0,02 % [14]. Измерение остаточного электросопротивления -чувствительный, точный и экспрессный метод позволяющий отслеживать структурные изменения в металлах и сплавах, следить за изменениями в концентрациях точечных дефектов на уровне ppm.…”

Section: материал и методикаunclassified

“…Облучение образцов нейтронами проводили в реакторе ИВВ-2М при 77 K в интервале флюенсов (1,(5)(6)(7)(8)(9)(10)(11)(12)(13)(14)(15)•10 18 см -2 . Наблюдавшийся при этом прирост относительного остаточного электросопротивления был существенно больше, чем при электронном облучении.…”

Section: результаты и обсуждениеunclassified

“…Подтверждено, что добавка в аустенитные стали фосфора приводит к выделению в них фосфидов [8,9], также способных играть роль прямых и косвенных стоков точечных де-фектов. Однако по поводу механизма этого явления высказываются различные мнения [10][11][12].…”

Section: Introductionunclassified

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Resistance-measurement studies of the peculiarities of the structural state of chromium-nickel-molybdenum austenitic reactor steels doped with titanium and phosphorus

Арбузов¹,

Бобровский²,

Danilov³

et al. 2017

DREAM

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Understanding of the mechanisms of radiation-induced phenomena is of fundamental value both for design of new steels and for improvement of the properties of the existing ones. Along with the crystal structure and chemical composition of the matrix, doping admixtures and the material microstructure play important role in these phenomena. In this paper, the p eculiarities of the microstructural state of chromium-nickel-molybdenum austenitic steels doped with titanium and phosphorus are studied by means of resistance measurements. The existence of the synergetic effects of simultaneous doping of steels with titanium and pho sphorus has been confirmed. The effect of solid solution segregation as the annealing temper ature reaches 700-800 K, accompanied by increasing electric resistivity, and has been found. The energies of the migration of interstitial atoms and of the dissociation of the "interstitial site -titanium atom" pair have been determined. The phenomena observed are in agreement with the results obtained for other austenitic steels. Keywords: austenitic reactor steels, segregation, intermetallics, doping, electrical resistance.DOI: 10.17804/2410-9908.2017.6.091-102 References 1.Zeman A., Kaiser R., Inozemtsev V., Beatty R.L. IAEA activities on coordinated research of structural materials for advanced reactor systems. J. Nucl. Mater., 2012, vol. 428, pp. 3-5. DOI: 10.1016/j.jnucmat.2012.024 2.Voyevodin V.N., Neklyudov I.M. Problems of radiation stability of structural materials for nuclear power industry. Visnyk Kharkivskogo Universitetu, ser. fiz., 2006, vol. 746, no. 4, pp. 3-22. (In Russian Voronin V.I., Arbuzov V.L., Bobrovskii V.I., Danilov S.E., Kozlov K.A., Proskurnina N.V., Sagaradze V.V. Peculiarities of radiation-induced processes in the Cr-Ni-Mo austenitic steels studied by neutron diffraction. Diagnostics, Resource and Mechanics of materials and structures, 2015, iss. 5, pp. 80-89. Available at: URL: http://dream-journal.org/issues/2015-5/2015-5_46.html (accessed 20.11.2017. 5.Sagaradze V.V., Nalesnik V.M., Lapin S.S., Aliabev V.M. Precipitation hardening and radiation damageability of austenitic stainless steels. J. Nucl. Mater., 1993, vol. 202, pp.137-144. DOI: 10.101690036-X 6.Okita T., Wolfer W.G., Garner F.A., Sekimura N. Effects of titanium additions to austenitic ternary alloys on microstructural evolution and void swelling. Philosophical Magazine, 2005Magazine, , vol. 85, no. 18, pp. 2033Magazine, -2048. DOI: 10.1080/14786430412331331871 7.Maziasz P.J. Formation and stability of radiation-induced phases in neutron irradiated austenitic and ferritic steels.

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Section: материал и методикаunclassified

Section: результаты и обсуждениеunclassified

Section: Introductionunclassified

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Resistance-measurement studies of the peculiarities of the structural state of chromium-nickel-molybdenum austenitic reactor steels doped with titanium and phosphorus

Арбузов¹,

Бобровский²,

Danilov³

et al. 2017

DREAM

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“…In order to retard the initiation time of steady void swelling and reduce the void swelling rate, minor elements are often added to a base alloy. 6,7) Especially, irradiationintroduced point defects strongly interact with added minor elements so that the defect accumulation behavior for the formation of dislocation loops and voids is influenced due to the interaction. 811) However, the comparative evaluation of the diffusion behavior which affects point defects accumulation behavior between steels with and without alloying minor elements has not been investigated.…”

Section: Introductionmentioning

confidence: 99%

Effect of Additional Minor Elements on Accumulation Behavior of Point Defects under Electron Irradiation in Austenitic Stainless Steels

et al. 2014

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Addition of minor elements to a base alloy is often applied with the aim of mitigating void swelling by decreasing the vacancy diffusivity and flux which influence vacancy accumulation behavior. However, the comparative evaluations of parameters, such as the diffusivity and flux, between a base alloy and modified alloys with specific additives have not been studied in detail. In this study, type 316 austenitic stainless steel as a base alloy and type 316 austenitic stainless steels modified with vanadium (V) or zirconium (Zr) additions were used to perform evaluations from the changes of widths of the void denuded zone (VDZ) formed near a random grain boundary during electron irradiation because these widths depend on vacancy diffusivity and flux. The formations of VDZs were observed in in-situ observations during electron irradiation at 723 K and the formed VDZ widths were measured from the transmission electron microscopic images after electron irradiation. As a result, the VDZs were formed in both steels without and with V, and respective widths were ³119 and ³100 nm. On the other hand, the VDZ formation was not observed clearly in the steel with Zr. From the measured VDZ widths in the steels without and with V addition, the estimated ratio of the vacancy diffusivity in the steel with V to that in the steel without V was about 0.50 and the estimated ratio of the vacancy flux in the steel with V to that in the steel without V was about 0.71. This result suggests that the effect of additional minor elements on vacancy accumulation behaviors under electron irradiation could be estimated from evaluations of the VDZ width changes among steels with and without minor elements. Especially, because void swelling is closely related with the vacancy diffusion process, the VDZ width changes would also be reflected on void swelling behavior.

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“…1) Neutron irradiation tests of the steel were performed and the samples of cladding tubes and plate shapes were found to have enough high temperature strength and swelling resistance. 2,3) On the other hand, when the same materials used for FBR fuel elements were irradiated, a large void swelling was observed even at low neutron doses. This phenomenon has been considered to be due to multiple effects of the irradiation environment, such as temperature variation during irradiation, a temperature gradient in the thickness direction, and the pressure applied by gaseous fission products.…”

Section: Introductionmentioning

confidence: 99%

Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel

Yamagata¹,

Akasaka²

2010

Journal of Nuclear Science and Technology

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Swelling behaviors in the wrapping wire and duct made of modified type 316 austenitic stainless steel were investigated in a fuel assembly irradiated in a fast breeder reactor. The temperature dependence of volumetric swelling was measured in the wrapping wire and the duct, and the peak temperatures of swelling were evaluated. The void distribution in the material was measured by microstructure observation with electron microscopy, and it was found that the voids prefentially grew near the surface. This phenomenon seemed to be caused by a surface effect on the neutron-irradiated materials.

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Swellling of advanced austenitic stainless steels developed for the environment of heavy neutron exposure

Cited by 25 publications

References 5 publications

Resistance-measurement studies of the peculiarities of the structural state of chromium-nickel-molybdenum austenitic reactor steels doped with titanium and phosphorus

Resistance-measurement studies of the peculiarities of the structural state of chromium-nickel-molybdenum austenitic reactor steels doped with titanium and phosphorus

Effect of Additional Minor Elements on Accumulation Behavior of Point Defects under Electron Irradiation in Austenitic Stainless Steels

Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel

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