EDN: BNGBWM
Authors & Affiliations
Gusev N.V., Pechenkin V.A., Folomeev V.I.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Gusev N.V. – Researcher.
Pechenkin V.A. – Leading Researcher, Cand. Sci. (Phys.-Math.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-80-19; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Folomeev V.I. – Leading Researcher.
Abstract
Stresses arising both during reactor and accelerator irradiation can have a significant impact on radiation phenomena in structural reactor materials (SM). The work proposes a methodology and carries out calculations of stresses caused by temperature gradients and implanted ions accumulation in samples made of austenitic (for example ChS68) and ferritic-martensitic (for example EP823) steels for typical conditions of irradiation with nickel and iron ions in the target device of Tandem-3M accelerator. For calculations by the finite element method (FEM) of temperature and stress fields, the
SIMULIA Abaqus code was used.
Calculations of temperature distribution in the target device and in samples made of EP823 and ChS68 steels under irradiation with Fe3+ and Ni3+ ions, respectively, with an energy of 11.5 MeV were carried out. The stresses caused by temperature gradients in the samples of both steels are small and do not exceed several MPa in the irradiation region. For the same irradiation conditions, FEM calculations of strains and stresses caused by ion implantation were carried out in samples of these steels at various damage doses up to 250 dpa. An analytical expression is obtained for the steady-state profile of stress intensity along the depth of the sample, determined by the ratio of ion implantation and radiation creep rates, which is in good agreement with the steady-state values calculated by FEM. Analytical estimates of possible local stresses associated with vacancy swelling of steels are obtained. These stresses are comparable with ones arising in the SM of fuel pin claddings at high doses of reactor irradiation.
For both steels considered, the stresses associated with ion implantation can be large, but they are localized in the zone of implanted ions accumulation. By choosing a relatively high ion energy
(5–12 MeV) for irradiation, it is possible to provide a sufficiently wide area for studying the microstructure of irradiated SM samples, remote both from the sample surface and from the region of high stresses in the implanted ions accumulation zone.
Keywords
accelerator irradiation, ion implantation, structural materials, EP823 and ChS68 steels, temperature gradients, strains, deformations
Article Text (PDF, in Russian)
References
- Grudzevich O.T., Pechenkin V.A., Kobetz U.A., Gurbich A.F., Bokhovko M.V., Shaginyan R.A., Margolin B.Z., Petrov S.N., Mikhailov M.S., Vasileva E.A. Issledovaniya radiatsionnoy stoykosti konstruktsionnykh materialov na uskoritelyakh ionov [Investigation of structural materials radiation resistance with ion accelerators]. Voprosy atomnoy nauki i tekhniki. Seriya: yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 3, pp. 127–145.
- Chernova A.D., Pechenkin V.A., Folomeyev V.I. Raschot temperatur i napryazheniy v obraztse pri ionnom obluchenii [Calculation of temperatures and stresses in a sample under ion irradiation]. Trudy XXVI Mezhdunarodnoy konferentsii “Radiatsionnaya fizika tverdogo tela” [Proceedings of the XXVI International Conference “Radiation Physics of Solid State”]. Moscow, Research Institute of PMT at MGIEM (TU), 2016, pp. 57–59.
- SRIM, Computer Code for Stopping and Range of Ions in Matter. Available at: http://www.srim.org (accessed 13.02.2024).
- Official electronic documentation for PC ABAQUS 6.13 (use license no. S100001227), Dassault Systèmes, 2013.
- Spravochnik po svoystvam materialov dlya perspektivnykh reaktornykh tekhnologiy. Tom 5. Svoystva reaktornykh staley i splavov. Pod obshchey redaktsiyey d.t.n., professora V.M. Poplavskogo [Reference book on properties of materials for advanced reactor technologies. Vol. 5. Properties of reactor steels and alloys. Ed. Dr. Sci. (Tech.), Professor V.M. Poplavsky]. Moscow, IzdAT Publ., 2014. 584 p.
- Teplofizicheskiye svoystva materialov yadernoy tekhniki. Spravochnik pod red. V.S.Chirkina [Thermophysical properties of nuclear technology materials. Handbook. Ed. V.S. Chirkin]. Moscow, Atomizdat Publ., 1968. 484 p.
- Fizicheskiye velichiny. Spravochnik pod. red. Grigor'yeva A.V. [Physical quantities. Handbook. Ed. Grigoriev A.V.]. Moscow, Energoatomizdat Publ., 1991. 1234 p.
- Pechenkin V.A., Chernova A.D., Molodtsov V.L., Garner F.A. Effect of internal sink strength on diffusion mass transport in alloys under high dose ion irradiation. Proceedings of the 12th International Topical Meeting on Nuclear Applications of Accelerators. November 10–13, 2015, Washington, USA, 2016, pp. 103–109.
- Flinn J.E., McVay G.L., and Walters L.C.In-reactor deformation of solution annealed type 304L stainless steel. Journal of Nuclear Materials, 1977, vol. 65, pp. 210–223.
- Margolin B.Z., Murashova A.I., Neustroyev V.S. Vliyaniye napryazheniy na radiatsionnoye raspukhaniye austenitnykh staley [Influence of stresses on radiation swelling of austenitic steels]. Voprosy materialovedeniya –Issues of Materials Science, 2011, no. 4(68), pp. 124–139.
- Porollo S.I., Shulepin S.V., Ivanov A.A. et al. Swelling and radiation creep of austenitic corrosion-resistant steel irradiated by neutrons in wide dose and temperature ranges. At Energy, 2011, vol. 110, issue 4, pp. 248–258. DOI: https://doi.org/10.1007/s10512-011-9419-z.
- Porollo S.I., Konobeev Y.V., Ivanov A.A. et al. Swelling and Radiation Creep of Ferrite-Martensite Steel Irradiated in the Bn-350 Reactor in a Wide Range of Temperature and Damaging Dose. At Energy, 2016, vol. 120, issue 3, pp. 189–198. DOI: https://doi.org/10.1007/s10512-016-0116-9.
- Polekhina N.A., Litovchenko I.Yu., Almayeva K.V., Tyumentsev A.N., Pinzhin Yu.P., Chernov V.M., Leont'yeva-Smirnova M.V. Sravnitel'noye issledovaniye mikrostruktury, mekhanicheskikh svoystv i osobennostey razrusheniya zharoprochnykh ferritno-martensitnykh staley EK-181, ChS-139 i EP-823 v intervale temperatury ot –196 do 720 °C [A comparative study of the microstructure, mechanical properties and fracture features of heat-resistant ferritic-martensitic steels EK-181, ChS-139 and EP-823 in the temperature range from –196 to 720 °C]. Voprosy atomnoy nauki i tekhniki. Seriya: termoyadernyy sintez – Problems of Atomic Science and Technology. Series: Thermonuclear Fusion, 2018, vol. 41, no. 4, pp. 38–47.
- Kruglov A.S., Bykov V.N., Pevchikh Y.M. Radiation creep in 09Kh16N15M3B steel at stresses exceeding the elastic limit. At Energy 1983, vol. 54, issue 2, pp. 62–63. DOI: https://doi.org/10.1007/BF01123715.
- Didenko A.N., Sharkeyev Yu.P., Kozlov E.V., Ryabchikov A.I. Effekty dal'nodeystviya v ionno-implantirovannykh metallicheskikh materialakh [Long-range effects in ion-implanted metal materials]. Tomsk, NTL Publishing House, 2004. 328 p.
- Garner F.A. Chapter 6: “Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors”. Materials Science and Technology: A Comprehensive Treatment, 1994, vol. 10a, pp. 419–543.
- Garner F.A., Toloczko M.B., Sencer B.H. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure. Journal of Nuclear Materials, 2000, vol. 276, pp. 123–142.
- Getto E., Sun K., Monterrosa A.M., Jiao Z., Hackett M.J., Was G.S. Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels. Journal of Nuclear Materials, 2016, vol. 480, pp. 159–176.
- Chuyev V.V. Povedeniye konstruktsionnykh materialov v spektre neytronov bystrogo reaktora bol'shoy moshchnosti. Avtoref. dokt. tekhn. nauk [Behavior of structural materials in the neutron spectrum of a high-power fast reactor. Author's abstract dr. sci. (tech.) diss.]. Zarechny, 2007, 44 p.
- Bakanov M.V., Nenakhov A.V., Dudnichenko I.S. Kontrol' rabotosposobnosti reaktornykh sborok posle ekspluatatsii v aktivnykh zonakh BN-600. Vtoraya modernizatsiya oborudovaniya “goryachey” kamery [Monitoring the performance of reactor assemblies after operation in the BN-600 cores. Second modernization of the hot cell equipment]. Yadernaya energetika. Izvestiya vuzov – Nuclear energy. News of Universities, 2009, no. 2, pp. 167–186.
- Vilenskiy O.Yu., Lapshin D.A., Ryabtsov A.V., Farakshin M.R. Termomekhanicheskoye vzaimodeystviye elementov teplovydelyayushchey sborki aktivnoy zony reaktorov tipa BN v usloviyakh vysokodoznogo oblucheniya [Thermomechanical interaction of elements in the core fuel assembly of BN-type reactors under high-dose irradiation conditions]. Voprosy atomnoy nauki i tekhniki. Seriya: yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 4, pp. 101–108.
- Tomoyuki Uwaba, Hiroyuki Ohshima, Masahiro Ito. Analyses of deformation and thermal-hydraulics within a wire-wrapped fuel subassembly in a liquid metal fast reactor by the coupled code system. Nuclear Engineering and Design, 2017, vol. 317, pp. 133–145.
- Akasaka N., Yamagata I., Ukai S. Effect of temperature gradients on void formation in modified 316 stainless steel cladding. Journal of Nuclear Materials, 2000, vol. 283–287, pp. 169–173.
- Seran J.L., Touron H., Maillard A., Dubuisson P., Hugot J.P., Le Boulbin E., Blanchard P., Pelletier M. The swelling behavior of titanium stabilized austenitic steels used as structural materials of fissile subassemblies in Phenix. Proc. of the 14th International Symposium “Effects of Radiation on Materials”: (Volume II). ASTM STP, vol. 1046, 1990, pp. 739–747.
- Tomoyuki Uwaba, Shigeharu Ukai. The secondary stress analyses in the fuel pin cladding due to the swelling gradient across the wall thickness. Journal of Nuclear Materials, 2002, vol. 305, pp. 21–28.
UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:12
