Assessment of WWER-1000 Core Baffle Form Alteration during Operation


reactor pressure vessel, baffle, in-vessel core barrel, core, fuel assemblies, stress-strain state, radiation-induced swelling, radiation swelling, creep, damaging dose, contact problem, finite element method.

How to Cite

Chirkov, A., Kharchenko, V., & Kobelsky, S. (2020). Assessment of WWER-1000 Core Baffle Form Alteration during Operation. Nuclear and Radiation Safety, (3(87), 13-20.


The paper illustrates the results of the computer assessment of the form alteration in WWER-1000 core baffle obtained via the solution to the coupled thermoelastoplastic task considering the strains of irradiation growth and creep. In the modeling of the contact conditions, the temperature redistribution is considered due to the incompliance of the coolant flow in the contact zone between the core baffle and in-vessel core barrel with the design conditions. The modern approaches to the modeling of strains of the irradiation growth and irradiation creep in austenite steels are used in the space-limited environment under neutron exposure and elevated temperature. The finite element analysis involves the mixed scheme of the finite element method, which allows determination of the stress-strain state with high accuracy. The calculations are performed in the two-dimensional statement for the cross-section of the core baffle with the maximum damaging dose and irradiation temperature under the condition of the generalized plane strain. The results of the calculations are presented for full-scale reactor operation and scheduled shutdown to recharge the fuel cluster at the end of core life. The data on the distribution and value of the gap between the core baffle and barrel, as well as the spacer grids of the edge fuel assemblies and reactor core baffle edges, have been obtained from the median values of the dose dependence on swelling at different temperatures in Kh18N10T austenite steel.


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