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Pressure vessel integrity assessment after long-term service irradiation is commonly based on surveillance program results. Nevertheless, only the investigation of RPV material from decommissioned NPPs enables the evaluation of the real toughness response. Such a chance is given now through the investigation of material from the former Greifswald NPP (VVER-440/230) to evaluate the material state of a standard RPV design and to assess the quality of prediction rules and assessment tools. The operation of the four Greifswald units was finished in 1991 after 12–15 years of operation. In autumn 2005 the first trepans (diameter 120 mm) were gained from the unit 1 of this NPP. Some details of the trepanning procedure will be given. The paper mainly deals with the retrospective dosimetry based on Niobium, which is a trace element of the RPV material. The reaction 93Nb(n,n′)93mNb with an energy dependence highly correlated to radiation damage and a half life of the reaction product of 16.13 years is well suited for retrospective fast neutron dosimetry. Fluence calculations using the code TRAMO were based on pin-wise time dependent neutron sources and an updated nuclear data base (ENDF/B-VI release 8). The neutron spectra were determined at the trepan positions. The different loading schemes of unit 1 (standard and with 4 or 6 dummy assemblies) were taken into account. The calculated specific 93mNb activities for February, 2006 at the sample positions were determined to 16.3 Bq/μg Nb for sample 1, (0.1cm distance from inner wall), and 4.0 Bq/μg Nb for sample 2 (11.5 cm distance from inner wall). Unfortunately, a second neutron reaction besides 93Nb(n,n′) leading to 93mNb-activity is the reaction 92Mo(n,γ)93Mo. 93Mo decays by electron capture to 93mNb with a half life of 4000 years and a branching ratio br = 0.88. As (n,γ)-reactions are produced mainly by low energy neutrons, being less important for material damage, the 93mNb-activity generated through the Mo-path should be determined separately and subtracted from the measured activity. For the sample 1 in the maximum flux azimuthal position of weld SN4 with a Nb-content of 8 ppm and an Mo-content of 4000 ppm for February 3, 2006 was obtained a Mo-induced 93mNb-activity of 80 Bq/g steel, amounting to 37.7% of the total 93mNb-activity. It turns out that the 93mNb generation on the second path is nearly of the same order as the fast neutron induced generation from Niobium. For the experimental determination of the 93mNb-activity the Nb-content was determined by ICP-MS (inductive coupled plasma mass spectrometry) after dissolution of the material sample. The radiochemical isolation of Nb was done by anion exchange separation. The radiochemical separation was accompanied by determination of the chemical yield of Nb using again the ICP-MS method. The measurement of the 93mNb activity was realized by Liquid Scintillation Spectrometry (LSC). The first comparison between the calculated and the measured 93mNb activities resulted in deviations between 15 and 50%. Possible reasons for the observed differences are discussed.

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The investigation of reactor pressure vessel (RPV) materials from decommissioned nuclear power plants (NPP) offers the unique opportunity to scrutinize the irradiation behavior under real conditions. The paper describes the investigation of trepans taken from the decommissioned WWER-440 RPVs of the Greifswald NPP. The key part of the testing is aimed at the determination of the reference temperature T0 following the ASTM Test Standard E1921 to determine the fracture toughness of the RPV steel in different thickness locations. In a first step, the trepan taken from the RPV Greifswald Unit 1 containing the multilayer welding seam located in the beltline region was investigated. This welding seam represents the irradiated, recovery annealed, and reirradiated condition. It is shown that the Master Curve approach as adopted in ASTM E1921 is applicable to the investigated original WWER-440 weld metal. The evaluated T0 varies through the thickness of the welding seam. After an initial increase of T0 from 10°C at the inner surface to 49°C at 22 mm distance from it, T0 decreases to −32°C at a distance of 70 mm, finally increasing again to 61°C near the outer RPV wall. The lowest T0 value was measured in the root region of the welding seam representing a uniform fine grain ferritic structure. The highest T0 of the weld seam was not measured at the inner wall surface. This is important for the assessment of ductile-to-brittle temperatures measured on subsize Charpy specimens made of weld metal compact samples removed from the inner RPV wall. Our findings imply that these samples do not represent the most conservative condition. Nevertheless, the Charpy transition temperature, TT41J, estimated with results of subsize specimens after the recovery annealing, was confirmed by the testing of standard Charpy V-notch specimens.

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