Characterization of Irradiation Damage of Ferritic ODS Alloys with Advanced Micro-Sample Methods

Oxide dispersion strengthened (ODS) steels are candidate materials for advanced electric energy and heat generation plants (nuclear, fossil). Understanding the degradation of mechanical properties of these alloys as a result of service exposure is necessary for safe design. For advanced nuclear applications combinations of temperature, irradiation and stress are important damage conditions. They are studied either with neutron irradiated samples (often highly active) or with ion-irradiated samples (irradiation damage often limited to only a few micrometer deep areas). High activity of samples and limited sample volume claim to subsized samples like nano-indentation, micro-pillar compression or thin strip creep testing. Irradiation hardening and irradiation creep were studied with these methods. Ferritic ODS steels with 19% chromium were investigated. The materials were studied in qualities differing in grain sizes and in sizes of the dispersoids. Irradiation was performed in an accelerator using He-ions. Irradiation damage profiles could be well analyzed with indentation. Yield stress determined with compression tests of single-crystal micropillars was well comparable with tension tests performed along the same crystallographic orientation. Irradiation creep of samples with different sizes of dispersoids revealed only a small influence of particle size being is in contrast with thermal creep but consistent with expectations from other investigation

New 2‑aminopyrimidine derivatives and their antitrypanosomal and antiplasmodial activities

Novel 2-aminopyrimidine derivatives were prepared from acyclic starting materials, benzylidene acetones and ammonium thiocyanates, via 5 steps, including ring closure, aromatization, S-methylation, oxidation to methylsulfonyl compounds, and formation of guanidines with suitable amines. The prepared compounds differ from each other by the substitutions of their amino group and of their phenyl ring. The 2-aminopyrimidines were tested by use of microplate assays for their in vitro activities against a causative organism of sleeping sickness, Trypanosoma brucei rhodesiense, as well as against a causative organism of malaria, Plasmodium falciparum NF54. Their cytotoxic properties were determined with L-6 cells (rat skeletal myoblasts). Some of the compounds exhibited quite good antitrypanosomal activity, and others showed excellent antiplasmodial activity. The influence of the structural modifications on these activities is discussed

ODS steel as structral material for high temperature nuclear reactors

Oxide dispersed strengthened (ODS) ferritic-martensitic steels are investigated as possible structural material for the future generation of High Temperature Gas Cooled Nuclear Reactors. The Ni based austenitic ODS superalloys are not considered, because of the Ni presence, which is unfavorable under neutron irradiation. ODS-steels are considered to replace other high temperature materials for tubing or structural parts. Interestingly, ODS is also considered as material being used in future fusion applications. The oxide particles serve for interfacial pinning of moving dislocations. Therefore the creep resistance is improved. In case of the usage of these materials in reactor, the behavior under irradiation must be further clarified. In this paper the effects induced by He implantation are investigated. The induced swelling is measured and the mechanical behavior of the irradiated surface is investigated. These first tests are performed at room temperature, where a clear swelling and hardening could be observed.Окисно дисперговані зміцнені (ОДЗ) феритно-мартенситні сталі досліджуються як можливі конструкційні матеріали для нового покоління високотемпературних ядерних реакторів з газовим охолодженням. Аустенітні ОДЗ-сплави на основі никелю не вивчаються завдяки никелю, присутність якого під дією опромінення небажана. ОДЗ-сталі разглядаються як можливі кандидати на заміну інших високотемпературних матеріалів для вигoтовлення трубопроводів або інших конструкційних вузлів. Цікаво, що ОДЗ-матеріали розглядаються також з точки зору їх можливого використання для майбутнього застосування в термоядерних пристроях. Окисні частки служать як міжфазні пастки для закріплення дислокацій, що рухаються. У разі використання ціх материалів в реакторі їх поведінка під опроміненням повинна вивчатись більш ретельно. В роботі досліджуються ефекти, зумовлені проникненням Не. Вимірюється зумовлене розпухання та механічні характеристики опроміненої поверхні. Ці перші дослідження були виконані при кімнатній температурі, коли можно чітко спостерігати розпухання та зміцнення.Окисно диспергированные упрочненные (ОДУ) ферритно-мартенситные стали изучались как возможные конструкционные материалы для нового поколения высокотемпературных ядерных реакторов с газовым охлаждением. Аустенитные ОДУ-суперсплавы на базе никеля не рассматривались из-за присутствия никеля, который нежелателен при нейтронном облучении. ОДУ-стали рассматривались как возможные заменители других высокотемпературных материалов для изготовления трубопроводов или других композиционных узлов. Интересно, что ОДУ рассматривается так же, как возможный кандидат для использования в термоядерных устройствах. Окисные частицы служат как межфазные ловушки для закрепления движущихся дислокаций. Поэтому сопротивление ползучести увеличивается. В случае использования этих материалов в реакторе их поведение под облучением должно изучаться более тщательно. В предлагаемой работе исследуются эффекты, обусловленные внедрением Не. Измеряется обусловленное распухание и механические характеристики облученной поверхности. Эти первые испытания были выполнены при комнатной температуре, когда можно явно наблюдать распухание и упрочнение

Unexpected ring‑opening of 2,3‑dihydropyridines

The reaction of 2,3-dihydropyridines with sulfonyl halides surprisingly yielded open chain dienes with sulfonylimine structure. The products were specific out of several possible isomers and, therefore, a separation of isomers was not necessary. All new compounds were characterized using FT-IR spectroscopy, HRMS, and NMR spectroscopy. A bicyclic by-product from the reaction of a 2,3-dihydropyridine with mesyl chloride was isolated and its structure elucidated using a single X-ray crystal analysis. Some biological activities, like antimicrobial and cytotoxic properties were investigated

In situ creep under helium implantation of titanium-aluminium alloy

The intermetallic alloy Ti-47Al-2W-0.5Si (at.%) has been homogeneously implanted with He-4(2+) ions under uniaxial tensile stresses from 20 to 450 MPa to a maximum dose of about 0.16 dpa (1370 appm-He) with displacement damage rates of 2 x 10(-6) dpa s(-1) at temperatures of 573 and 773 K. Strain under implantation was determined by Linear Variable Displacement Transformer (LVDT), while changes of microstructure were investigated after implantation by Transmission Electron Microscopy (TEM). Irradiation creep strain showed a pronounced transient behaviour, virtually independent of temperature, with a stress dependence which can be approximately described by a creep compliance of 8 X 10(-6) dpa(-1) MPa-1 up to stresses of 350 MPa. The microstructure of the as-received material consisted of a patch-work of mainly lamellar gamma/alpha(2) colonies and equiaxed gamma-grains with islands of precipitates. Only 'black dot' damage was observed after implantation at 573 K under different stresses, while implantation at 773 K yielded a dense population of bubbles and dislocation loops, mostly mutually attached. (c) 2006 Elsevier B.V. All rights reserved

Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress

The oxide dispersion strengthened (ODS) ferritic steel PM2000, was homogeneously implanted with alpha-particles under uniaxial tensile stresses ranging from 20 to 250 MPa, causing irradiation creep. The irradiation temperatures were 573, 673, and 773 K, respectively. Maximum helium concentrations of 3000 appm were attained, causing a concurrent displacement dose of approximately 0.75 dpa (damage rate about 5x10(-6) dpa s(-1)). Microstructural changes were studied in detail by transmission electron microscopy (TEM). Two sets of dislocation loops were identified, both interstitial in nature, with Burgers vectors b= and b=1/2 , and habit planes of (100) and (111), respectively. No influence of stress applied during the irradiation creep tests on loop formation and growth could be detected. TEM investigation also showed the formation of bubbles attached to loops already during implantation at 573 K, the formation of bubble-loop complexes at 673 K, and Y2O3 particles changing their shape by the attachment of bubbles at 773 K. (c) 2007 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved

Recycling of hazardous solid waste material using high-temperature solar process heat. 1. Thermodynamic analysis

The thermochemical conversion and recycling of hazardous solid waste materials is investigated using high-temperature solar process heat. Two important sources of wastes contaminated with heavy metal oxides are considered: (1) electric are furnace dust (EAFD) and (2) automobile shredder residue (ASR). The chemical equilibrium composition of these complex materials and the energy required to process them, using carbon, methane, or pyre-coke as reducing agents, are computed for temperatures in the range 300-2000 K. Metals can be extracted from their oxides in reducing atmospheres at above 1300 K for both EAFD and ASR: Zn is obtained in the gas phase, while Fe, Pb, and Cu are obtained in the condensed phase. The thermal energy requirements for converting EAFD at 1500 K are 3008 kJ/ kg and 4143 kJ/kg using C(gr) and CH4 as reducing agents, respectively. For converting ASR at 1500 K, 2455 kJ/kg are required. The solar exergy conversion efficiency, i.e., the efficiency of converting solar energy into the chemical energy of the reaction products (given by the Gibbs free energy change of product oxidation), can be as high as 69% for the EAFD conversion and 87% for the ASR conversion. Major sources of irreversibilities are those associated with the reradiation losses of the solar reactor and the heat rejected during the quenching. The use of concentrated solar energy as the source of process heat avoids emissions of greenhouse gases and other pollutants derived from the combustion of fossil fuels and further offers the possibility of converting waste materials into valuable commodities for processes in closed and sustainable materials cycles

Irradiation creep and precipitation in a ferritic ODS steel under helium implantation

Ferritic oxide dispersion strengthened (ODS) steel, PM2000, has been homogeneously implanted with helium under uniaxial tensile stresses from 20 to 250 MPa to maximum doses of about 0.75 dpa (3000 ppm He) with displacement damage rates of 5.5 x 10(-6) dpa/s at temperatures of 573, 673 and 773 K. Straining of a miniaturized dog-bone specimen under helium implantation was monitored by linear variable displacement transformer (LVDT) and meanwhile by their resistance also measured by four-pole technique. Creep compliance was almost constant at 5.7 x 10(-6) dpa(-1) MPa-1 for temperatures below 673 K and increased to 18 x 10(-6) dpa(-1) MPa-1 at 773 K. The resistivity of PM2000 samples decreased with dose and showed a tendency to saturation. Subsequent transmission electron microscopy observations indicated the formation of ordered Fe3-xCrxAl precipitates during implantation. Correlations between the microstructure and resistivity are discussed. (c) 2007 Elsevier B.V. All rights reserved