The properties of WWER-440 type reactor pressure vessel steels cut out from operated units

This paper presents the results of study on radiation degradation occurring in WWER-440 reactor pressure vessel (RPV) steel, using subsize impact specimens (5×5×27.5 mm³). The results of testing trepans and templates cut out from WWER-440 reactor pressure vessels are considered. Ductile-to-brittle transition temperatures (DBTT) obtained using standard Charpy and subsize impact specimens are compared. The relation between these two values is established.     

Fluoxetine induced insulin-like growth factor II (IGF-II) changes in hypothalami of normal, exercised and food restricted rats

Hypothalamic and pituitary insulin-like growth factor II (IGF-II) peptide concentrations are differentially regulated by factors associated with metabolism such as insulin and glucoprivation. However, the effects of other metabolic stressors such as food restriction or exercise on hypothalamic IGF-II concentrations remain largely to be explored. In order to assess whether metabolic stress alters central nervous system IGF-II secretion, peptide analysis was conducted in rats exhibiting activity-based anorexia (ABA) compared to exercised-matched, body weight-matched or ad libitum fed controls. Further, the possibility of serotonergic control of IGF-II secretion was examined by determining IGF-II response to fluoxetine (FLX) injections (15 mg/kg body wt., i.p.). While ABA and body weight loss altered peripheral IGF-II concentrations compared to ad libitum fed or exercised controls, these treatments had no effect on hypothalamic or posterior pituitary IGF-II content. However, FLX administration increased IGF-II concentrations in the ventromedial hypothalamus and decreased IGF-II content in the lateral hypothalamus compared to vehicle injected. Anterior pituitary levels of IGF-II were also decreased by FLX. These data suggest that a serotonergic influence on CNS IGF-II exists and that IGF-II secretion may be altered by factors affecting serotonin metabolism or efficacy.     

Verformungsbezogene mittragende Breite niedriger Verbundträger

Effective width due to deflections of composite girders with shallow height. Due to the high slenderness of composite girders with shallow height their deflection behaviour is of great importance. In many cases the cross sectional dimensions are determined by the limitation of the deflections. In contrary to high composite beams the deflection behaviour of these girders is influenced especially by the bending state and cracking behaviour of the concrete slab. Among others the deflection or the stiffness of the composite girders depend on the effective width of the slab. This article reports on investigations of the deflection behaviour and the effective width of shallow composite girders taking into account the bending state and the cracking of the concrete slab. At first it is shown that for the calculation of stresses a different value of the effective width has to be taken into account than for the calculation of deflections. On basis of extensive experimental, analytical and numerical investigations the influences on the effective width are analysed. A wide‐ranging parametric study leads to the development of an approach of the effective width for the calculation of deflections and a proposal for a quasi‐elastic calculation of the deflections of shallow composite girders. At this it turns out that the effective width due to deflections is influenced above all by the bending state of the concrete slab, its cracking behaviour, its ratio width to length, the ratio of the individual stiffness components of the composite cross section and the load level. On basis of the proposed approach for the calculation of the effective width the deflections of shallow composite girders can be determined realistically. This leads to a more economic design of composite shallow girders than until now.     

Paraventricular hypothalamic clonidine increases rather than decreases susceptibility to activity-based anorexia in the rat.

Anorexia has been related to reduced activity of the paraventricular hypothalamic (PVN) noradrenergic-feeding system. This study attempted to determine whether clonidine (an α2-adrenergic agonist) infused into the PVN reduced susceptibility to activity-based anorexia (ABA) in the rat. In Exp 1, clonidine (6 doses) was chronically infused into the PVN of male Sprague-Dawley rats. All animals were exposed to ABA (1.5 hrs/day food access; 22.5 hrs/day running wheel access) until a 25% body weight loss was reached. Dose-related increases in susceptibility to ABA and decreases in food intake were observed. In Exp 2, for which heavier animals and 3 doses of clonidine were used, no difference was found in food intake and wheel activity, but there was increased susceptibility to ABA. Chronic clonidine infused into the PVN does not produce hyperphagia and exacerbates rather than attenuates susceptibility to ABA. (PsycINFO Database Record (c) 2010 APA, all rights reserved)     

Untersuchung des Einflusses von Radkörperstrukturen auf das Einsatzverhalten von Zahnrädern

Forschung im Ingenieurwesen - Die steigenden technischen und wirtschaftlichen Anforderungen an Leistungsgetriebe führen zu einem kontinuierlichen Optimierungsbedarf in der Getriebeauslegung....     

Neutron Embrittlement of WWER Reactors: EC-Supported Projects

Results of the implementation of programs on the evaluation of the service life of reactor pressure vessels of NPPs are considered with the account of neutron embrittlement. Data on strength of WWER-440 reactor pressure vessels with a high and moderate content of detrimental impurities (copper and phosphorus) have been analyzed. For the welds of WWER-1000 reactor, drawbacks in the manufacture, dosimetry, and test procedures of surveillance specimens are shown. To ensure safe operation of reactor pressure vessels, new projects have been undertaken, focusing on the effect of neutron embrittlement of steel on the integrity of structures and on advanced experimental methods of studying material strength.     

Neutron embrittlement of VVER reactor pressure vessels—recent results, open issues and new developments

Decisions regarding the verification of design plant lifetime involve a determination of the component and circuit condition. Neutron embrittlement of reactor pressure vessels (RPV) becomes a crucial consideration for continued safe plant operation. Since 1991, the European Commission (EC) has financed a significant number of projects in this area, in particular through the TACIS and PHARE programmes. In Nuclear Safety support programmes the countries mainly concerned are Russia, Ukraine, Armenia, and Kazakhstan for the TACIS programme, and Bulgaria, Czech Republic, Hungary, Slovak Republic, Lithuania, Romania and Slovenia for the PHARE programme. The corresponding results of these projects on neutron embrittlement have contributed to a better understanding of the available data and their uncertainties. Recent confirmations of the irradiation temperatures of the surveillance specimens in the operating VVER nuclear power plants show that the surveillance specimens can be used further for the validation of the current and the expected neutron embrittlement. Taking into account the latest results as a baseline for the development of the necessary material data to be used for upgraded RPV integrity assessment, two new TACIS projects are being launched, jointly with Russia and Ukraine, whose scope is:

• Upgrading the surveillance databases.

• Acquisition of new impact test and toughness results on reconstituted surveillance specimens, including the evaluation of the Mater Curve Approach.

• Further validation tests of the shape of the fracture toughness curve and the base and weld metal and characterization of the cladding.

• Preparation of some selected upgraded RPV integrity assessments, with insights on the latest approved methodology.

The paper summarizes the major conclusions of the recent completed EC projects, reviews the remaining major open issues in the field of reliable determination of fracture toughness properties of the operating VVER RPVs, and details the scope of the new projects.     

Investigation of samples taken from Kozloduy unit 2 reactor pressure vessel

Within the framework of the 6 month WANO program, small samples were cut from the inside surface of the Kozloduy NPP unit 2 reactor pressure vessel to assess the actual condition of the pressure vessel material before and after annealing. The actual values of the weld metal characteristics required for estimating radiation-limited lifetime—the ductile-to-brittle transition temperature (DBTT) in the initial state (T_ko) and the phosphorus and copper contents which affect the radiation stability of steel—were not determined during manufacturing. The Kozloduy unit 2 pressure vessel had no surveillance program. Radiation stability was evaluated using dependencies based on analysis results for surveillance samples taken from other VVER-440 reactors. For this reason, the actual pressure vessel characteristics and their changes in the course of reactor operation, as well as comparison of experimental with calculated data were the principle objectives of the study.Instrumented impact tests were carried out on sub-size specimens of base and weld metal. Correlation dependencies were used with standard tests to determine DBTTs for the base and weld metal (in accordance with Russian standards): base metal before annealing 40 °C, after annealing 16 °C; weld metal before annealing 212 °C, after annealing 70 °C.The estimated value of T_ko, for the initial, unirradiated weld metal, was 50 °C. The experimental results were compared with a prediction of the extent of radiation-induced embrittlement of Kozloduy unit 2 pressure vessel materials. It was confirmed that radiation-induced embrittlement of the base metal does not impose any limits on the radiation-limited lifetime of the pressure vessel.The predicted increase in the DBTT of the weld metal as a result of irradiation (about 165 °C) is practically equal to the experimental result (162 °C). However, the value of T_f obtained from tests before annealing (212 °C) is about 40 °C higher that the estimated value, i.e. the calculation does not produce a conservative estimate. This was explained by a low estimate of T_ko (10 °C), which had been calculated using data from chemical analysis of the weld metal, performed by the manufacturer. The investigations on the samples, however, yielded an estimated value of T_ko = 50 °C.The effectiveness of annealing in restoring the mechanical properties of irradiated VVER-440 reactor pressure vessels was confirmed. Recovery annealing lowered the DBTT of the weld metal by 85% or more of its radiation-induced shift.