Affiliation:
1. National University of Science and Technology “MISIS”
2. National University of Science and Technology “MISIS”; Baikov Institute of Metallurgy and Materials Science, Russian Academy of Sciences
3. Academician I.V. Gorynin Central Research Institute of Structural Materials “Prometey”, National Research Center “Kurchatov Institute”
Abstract
The Russian new nuclear reactors are provided with a special core catcher vessel device (cc-vessel) designed to minimize the consequences of a severe beyond design basis accident at a nuclear power plant, when the reactor pressure vessel collapses and the core melts. For manufacture of the cc-vessel structural elements, low-carbon unalloyed or low-alloyed steels are used. When a severe beyond design basis accident develops, the cc-vessel’s body is subjected to extreme temperature and force loads, which can lead to degradation of the structure, loss of strength and failure of the entire cc-vessel. To calculate the strength characteristics of the cc-vessel, which ensure its safe and reliable operation, the detailed data are required on the structure and mechanical properties of low-carbon steels at high temperatures and after extreme thermal actions simulating the development of a severe beyond design basis accident. The paper analyzes data on the structure and mechanical properties (tensile strength, crack resistance, toughness and cyclic strength) of a number of low-carbon steels under extreme temperature and force actions, including conditions simulating the development of a severe beyond design basis accident at a nuclear power plant, in order to select the material for the design of cc-vessel of nuclear reactor. New data on the structure, mechanical properties, and thermal diffusivity in a wide temperature range of a Cr – Mo steel (Russian Standard – 15KhM) as a candidate structural material for the manufacture of the cc-vessel body are presented. The low content of manganese and alloying with molybdenum and vanadium in 15KhM steel provides a finer grained structure and eliminates the steel’s tendency to temper brittleness.
Publisher
National University of Science and Technology MISiS
Reference33 articles.
1. Artamonov N.V., Sidorov A.S. Nuclear safety of melt localisator device for NPP with WWER reactor model. Izvestia vuzov. Yadernaya energetica. 2012;(3):23–31. (In Russ.).
2. Sidorov A.S. Core catcher vessel for nuclear power plants with VVER-1000 reactors. In: 7th Int. Sci. and Tech. Conf. “Ensuring the Safety of Nuclear Power Plants with VVER”. Podolsk: OKB Gidropress: 2011. (In Russ.).
3. Rempe J.L., Knudson D.L., Condie K.G., Suh K.Y., Cheung F.-B., Kim S.-B. Conceptual design of an in-vessel core catcher. Nuclear Engineering and Design. 2004;230(1–3): 311–325. https://doi.org/10.1016/j.nucengdes.2003.11.030
4. Sultan T., Sapra M.K., Kundu S., Kadam A.V., Kulkarni P.P., Rao A.R. Experimental & analytical study of passive thermal sensing system developed for cooling water injection into AHWR core catcher. Nuclear Engineering and Design. 2017;322:81–91. https://doi.org/10.1016/j.nucengdes.2017.06.021
5. Rempe J.L., Knudson D.L., Condie K.G., Suh K.Y., Cheung F.-B., Kim S.-B. Corium retention for high power reactors by an in-vessel core catcher in combination with external reactor vessel cooling. Nuclear Engineering and Design. 2004;230(1–3):293–309. https://doi.org/10.1016/j.nucengdes.2003.11.031