Abstract
Radiation embrittlement of VVÉR-1000 vessel materials has been studied much less than for VVÉR-440 reactors. In the present paper the results of an investigation of the first batches of control samples of VVÉR-1000 vessel materials are discussed. The chemical composition of the materials is characterized by a low content of harmful impurities (copper and phosphorus) and a high nickel content (up to 1.9% in some weld seams). The actual rate of radiation embrittlement of the material studied is comparable to the embrittlement calculated using the Russian standards. The dependence of radiation embrittlement of VVÉR-1000 vessel materials on the metallurgical variables and the damaging dose is studied. The investigation showed that nickel greatly intensifies the radiation embrittlement. New relations were developed for determining the actual rate of radiation embrittlement of VVÉR-1000 reactor vessel materials and assessment of its conservativeness.
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REFERENCES
J. Hawthorne, “Irradiation embrittlement,” in: Treatise on Materials Science and Technology (1983), Vol. 25, pp. 461-524.
N. N. Alekseenko, A. D. Amaev, I. V. Gorynin, and V. A. Nikolaev, Radiation Damage to Water-Moderated Water-Cooled Reactor Vessel Steel [in Russian], Énergoatomizdat, Moscow (1981).
A. D. Amaev, A. M. Kryukov, V. I. Levit, and M. A. Sokolov, “Radiation stability of VVÉR-440 vessel materials,” in: Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels, ASTM STP 1170 (1993), pp. 9-29.
Yu. A. Nikolaev, A. V. Nikolaeva, A. M. Kryukov, et al., “Radiation embrittlement and thermal annealing of behavior of Cr-Ni-Mo reactor pressure vessel materials,” J. Nucl. Mater., 226, 144-155 (1995).
A. M. Kryukov, Yu. A. Nikolaev, and A. V. Nikolaeva, “Behavior of mechanical properties of nickel-alloyed reactor pressure vessel steel under neutron irradiation and post-irradiation annealing,” Nucl. Eng. Design, 186, 353-359 (1998).
Standards for Strength Calculations of Equipment and Pipelines in PNAÉ Nuclear Power Systems G-7-002-86 [in Russian], Énergoatomizdat, Moscow (1989).
A. M. Kryukov, Yu. A. Nikolaev, T. Planman, and P. A. Platonov, “Basic results of the Russian VVÉR-1000 surveillance program,” Nucl. Eng. Design, 173, 333-339 (1997).
Yu. A. Nikolaev and A. V. Nikolaeva, “Application of the floating curve model for estimation of re-irradiation embrittlement of VVÉR-440 RPV steels,” in: Effects of Radiation on Materials ASTM STP 1366 (2000), pp. 460-470.
V. N. Golovanov, N. V. Markina, V. M. Raesty, et al., “Irradiation of vessel materials using KORPUS facility of RBT-6 reactor,” in: Effects of Radiation on Materials ASTM STP 1325 (1999), pp. 233-245.
T. Planman, Yu. A. Nikolaev, A. M. Kryukov, and V. A. Nikolaev, “Evaluation of irradiation embrittlement of Russian WWER-1000 reactor pressure vessel beltline steels,” Report VALC325, VTT Manufacturing Technology, Espoo, Finland, February 1997.
A. V. Nikolaeva and Yu. A. Nikolaev, “Mechanism of the drop in the dependence of the yield stress on neutron irradiation dose for low-alloy steel,” Mater. Sci. Eng. A, 234-236, 915-917 (1997).
M. Akamatsu, J. C. Van-Duysen, P. Pareige, and P. Auger, “Experimental evidence of several contributions to the radiation damage of ferritic alloys,” J. Nucl. Mater., 225, 192-195 (1995).
M. Davies, A. Kryukov, C. English, and Yu. Nikolaev, “East/West steels for reactor pressure vessels,” in: Irradiation Effects and Mitigation, Proceedings of the IAEA Specialists Meeting Held in Vladimir, Russian Federation (1997), IWG-LMNPP-97/2, pp. 42-61.
Yu. A. Nikolaev, A. V. Nikolaeva, and A. M. Kryukov, “The nickel effect on mechanical property recovery under post-irradiation annealing,” in: Fourth International Conference on Materials Science Problems in NPP Equipment Production and Operation, St. Petersburg, Russia (1996), Vol. 1, pp. 231-235.
L. M. Utevskii, E. É, Glikman, and G. S. Kark, Reversible Temper Brittleness of Steel and Iron Alloys [in Russian], Metallurgiya, Moscow (1987).
Yu. A. Nikolaev and A. V. Nikolaeva, “Embrittlement of low-alloyed steels due to impurity segregation at intergranular boundaries,” Material Science Forum, 207-209, 653-656 (1996).
A. V. Nikolaeva and Yu. A. Nikolaev, “Kinetics of radiation-stimulated grain-boundary adsorption of phosphorous in low-alloy steels,” in: Fourth International Conference on Materials Science Problems in NPP Equipment Production and Operation, St. Petersburg, Russia (1996), Vol. 3, pp. 18-26.
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Nikolaeva, A.V., Nikolaev, Y.A. & Kevorkyan, Y.R. Radiation Embrittlement of VVÉR-1000 Vessel Materials. Atomic Energy 90, 374–381 (2001). https://doi.org/10.1023/A:1011320424376
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DOI: https://doi.org/10.1023/A:1011320424376