Investigation of in-reactor creep and irradiation growth of zirconium-2.5 wt% niobium channel tubes |
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Authors: | VV Goncharov PA Platonov AN Ivanov IA Frolov |
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Affiliation: | Kurchatov Institute of Atomic Energy, Moscow, USSR |
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Abstract: | We summarize the diametral creep results obtained in the MR reactor of the Kurchatov Institute of Atomic Energy on zirconium-2.5 wt% niobium pressure tubes of the type used in RBMK-1000 power reactors. The experiments that lasted up to 30 000 h cover a temperature range of 270 to 350°C, neutron fluxes between 0.6 and 4.0 ×1013 n/cm2 · s (E > 1 MeV) and stresses of up to 16 kgf/mm2. Diametral strains of up to 4.8% have been measured. In-reactor creep results have been analyzed in terms of thermal and irradiation creep components assuming them to be additive. The thermal creep rate is given by a relationship of the type εth = A1 exp (A2 + A 3σt) T] and the irradiation component by εrad = A4σtø(T ? A5), where T = temperature, σt = hoop stress, ø = neutron flux and a1 to A5 are constants. Irradiation growth experiments carried out at 280° C on specimens machined from pressure tubes showed a non-linear dependence of growth strain on neutron fluence up to neutron fluences of 5 × 1020 n/cm2. The significance of these results to the elongation of RBMK reactor pressure tubes is discussed. |
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