ДОСЛІДЖЕННЯ МЕТОДОМ КЛАСТЕРНОЇ ДИНАМІКИ ВПЛИВУ ЗМІНИ ТЕМПЕРАТУРИ НА НЕЙТРОННУ КРИХКІСТЬ α-ЗАЛІЗА
##plugins.themes.bootstrap3.article.main##
Анотація
Метод кластерної динаміки використовується для моделювання впливу температури на зростання межі текучості, яке зумовлено нейтронним опромінюванням. Показана необхідність врахування зміни температури при використанні даних про нейтронну крихкість зразків-свідків для оцінки механічних властивостей корпусу атомного реактору при робочій температурі.
##plugins.themes.bootstrap3.article.details##
Посилання
Gokhman A., Bergner F. (2010). Cluster dynamics simulation of point defect clusters in neutron irradiated pure iron. Radiation Effects and Defects in Solids: Incorporating Plasma Science and Plasma Technology, 165, 216–226.
Shu S., Almirall N, Wells P., Yamamoto T., Odette G., Morgan D. (2018). Precipitation in Fe-Cu and Fe-Cu- Mn model alloys under irradiation: Dose rate effects. Acta Materialia, 157, 72-82.
Bergner F., Gillemot F., Hernández-Mayoral M., Serrano M., Török G., Ulbricht A., Altstadt E. (2015.) Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels, Journal of Nuclear Materials, 461, 37–44.
Meslin E., Lambrecht M, Hernandez-Mayoral M, Bergner F. (2010). Characterization of neutron-irradiated ferritic model alloys and RPV steel from combined APT, SANS, TEM and PAS analyses, Journal of Nuclear Materials, 406, 73-83.
Jumel S., Duysen Van J. (2007), Simulation of irradiated effects in light water reactor vessel steels – experimental validation of RPV-1, Journal of Nuclear Materials, 366, 256-265
Ulbricht A., Altstadt E., Bergner F., Viehrig H., Keyderling U. (2011). Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor, Journal of Nuclear Materials, 416, 111-116.
Kondria M., Gokhman A. Cluster dynamics simulation of the flux effect for neutron irradiated pure iron, in print
Becker J., Becker E., Brandes Re. (1961). Reactions of Oxygen with Pure Tungsten and Tungsten Containing Carbon, J. Appl. Phys., 32, 411-423.
Odette G. R. (1998). Neutron irradiation effects in rea pressure vessel steels and weldments. In: Davies, M.(Ed.), Modeling Irradiation Embrittlement in Reactor Pressure Vessel Steels. Vienna, 438-530.
Hindmarsh A. C. (1983) ODEPACK. A Systematized Collection of ODE Solvers. Scientific Computing, R. S. Stepleman et al. (eds.), North-Holland, Amsterdam, Vol. 1 (of IMACS Transactions on Scientific Computation), 55-64.
Petzold L. R. (1983). Automatic selection of methods for solving stiff and nonstiff systems of ordinary differential equations. Siam J. Sci. Stat. Comput, Vol. 4, P. 136-148.
The NAG Fortran Library www.nag.co.uk https://www.nag.co.uk/nag-fortran-library
LSODA is part of the ODEPACK provided by Alan C. Hindmarsh (1984) on the CASC server of the Lawrence Livermore National Laboratory, Livermore, CA 94551, USA.
Amosov A. A., Kopchenova N. V., Dubinsky Yu. A. (1994). Computational methods for engineers, M .: Higher School, 544 p.
Hardouin Duparc A,. Moingeon C., Smetaninsky-de-Grande N., BarbuA. (2002). Microstructure modelling of ferritic alloys under high flux 1MeV electron irradiations, Journal of Nuclear Materials, 302, 143–155.
Bergner F., Almazouzi A., Hernandez-Mayoral M., Lambrecht M., Ulbricht A. (2008) In Combined TEM, PAS and SANS Investigations of Neutron Irradiated Pure Iron WorkshopProceedings Karlsruhe, Germany, 2007, June 4–6, Nuclear Energy Agency, 260, OECD, 283–290.