Protein organization on the PHA inclusion cytoplasmic boundary

Biotransformation of ethanol by liver nuclei was studied. The formation of acetaldehyde was determined by GC/FID. The 1-hydroxyethyl (1HEt) formation was established by spin trapping of the radical with N-t-butyl-alpha-phenylnitrone (PBN) followed by GC/MS. Liver nuclei, free of endoplasmic reticulum, cytosol or mitochondria, were able to biotransform ethanol to acetaldehyde in the presence of NADPH under air. Only 22% activity was observed in the absence of the cofactor. Twenty-six percent of the NADPH-dependent activity and 47% of the NADPH-independent activity were observable under nitrogen. Aerobic biotransformation was inhibited by CO, SKF 525A, 4-methylpyrazole and by diethyldithiocarbamate. This suggests that CYP2E1 is involved in the process. However, the formation of acetaldehyde was able to proceed under a pure CO atmosphere. The lack of inhibitory effects of 2-mercapto-1-methylimidazol and thiobenzamide excludes the potential participation of the NADPH flavin monooxigenase system. The formation of hydroxyl radicals in the process is suggested by the partial inhibitory effect of 5 mM mannitol and 5 mM sodium benzoate and by the fact that the 1HEt was detected. The NADPH-dependent anaerobic ethanol biotransformation pathway was stimulated by FAD and inhibited to some extent by iron chelators. The relevance of a liver nuclear ethanol biotransformation, generating reactive metabolites, such as acetaldehyde and free radicals, nearby DNA, nuclear proteins and lipids is discussed.     

Application of annealing for extension of WWER vessel lives

The safe operation of nuclear power plants (NPP) is dependent upon the assurance that the reactor pressure vessel will not fail in a brittle manner when the effects of radiation embrittlement are taken into account. The recovery of the properties of the irradiated materials is an important way of extending the operating life of a reactor vessel. The intent of this paper is to demonstrate the efficiency of thermal annealing for the recovery of reactor vessel material properties and to present the implications for extended service life.In order to substantiate the application of annealing to the extensior of the service life of vessels, detailed investigations were conducted which involved thermal annealing temperature and time, fast neutron fluence, and metallurgical factors (i.e. impurity contents) on the recovery of properties after the annealing of irradiated materials. Similar studies were continued to determine predictive methods for radiation embrittlement after repeated annealings.In May 19876 the first pilot annealing of a commercial reactor vessel (Novo-Voronezhskaya, III, NPP) was performed. The development of the annealing equipment and investigations performed to test the annealing process proved successful, and an improved safe operation period for the reactor vessel was thus attained providing for an extended service life.     

Mechanical testing of plasma-sprayed coatings of ceramics

Mechanical tests have been performed on two types of plasma-sprayed ceramic coatings: magnesium zirconate (ZM) on aluminium alloy and chromium oxide (CO) on cast iron. Tensile strength, shear strength, energy relaxation rate and crack velocity have been determined. Results obtained with double-torsion tests show good agreement with those of double-cantilever-beam tests. Fracture always occurred in the ceramic for the ZM coating and at the interface for the CO one. Finally, acoustic emission monitoring carried out during bending tests was used to point out different types of emission, and to correlate them with micrographic examinations in order to identify some damaging processes.[/p]     

Entkohlungsreaktionen mit unruhigem Blasverhalten beim Aufblasen von Sauerstoff auf Fe-C-Schmelzen

Reaktionen in der Gasphase und an der Badoberfläche. Filmaufnahmen von pulsierenden Vorgängen. Entkohlungsreaktionen nach Art von Siedeverzügen. Ruhiges und unruhiges Blasverhalten. Abgas- und Brennflecktemperaturen. Kleinkonverter- und Induktionsofenversuche.     

Spatial distributions of residuals produced inside a spallation target

The spallation target model of an accelerator driven system (ADS), consisting of six 5 cm thick and 16 cm in diameter Pb segments, was constructed. Three sets of 17 Bi samples (1/2 inch in diameter and 1 mm thick) were placed in 3 Pb disc-shaped holders inside the target at 5, 10 and 15 cm from its front. After irradiation with 660 MeV proton beam gamma-spectra of radioisotopes produced in Bi were collected several times for each sample with the use of HPGe detectors in order to identify the radioisotopes and to determine their absolute activities. Their spatial distributions were then compared with respective values obtained in the calculations made with the use of FLUKA and/or MCNPX code. A fair agreement with the experiment has been observed.     

Microstructure, Chemical and Phase Composition of Chromium Silicide Diffusion Coatings on Carbon Steels

The microstructure, chemical and phase composition of chromium silicide diffusion coatings on steels 20, 45, U8, and U10 are studied. It is established that the phases Cr²³C⁶ and Cr⁷C³ with a silicon content in them of up to 0.25 at.% form at the surface of chromium silicide coatings. The maximum silicon content at 7% in steels 20 and 45 is observed beneath the carbide layer at a depth of 40–50 µm, but for steel U10 it is 1.9% at the carbide layer-matrix boundary. It is shown that the corrosion resistance of chromium silicide diffusion coatings increases markedly compared with uncoated specimens: by a factor of 15–30 depending on the acid used (H₂SO₄, HCl, H₃PO₄, HNO₃, CH₃COOH). There is also an increase in the cavitation resistance of articles with chromium silicide coatings in water and 3% NaCl solution.__________Translated from Poroshkovaya Metallurgiya, Nos. 1–2(441), pp. 23–30, January–February, 2005.     

Prevention of high-dose-rate brachytherapy accidents. ICRP Publication 97

High-dose-rate brachytherapy is a rapidly growing technique (HDR) that has been replacing low-dose-rate (LDR) procedures over the last few years in both industrialised and developing countries. It is estimated that about 500,000 procedures (administration of treatment) are performed by HDR units annually. LDR equipment has been discontinued by many manufacturers over the last few years, leaving HDR brachytherapy as the major alternative. HDR brachytherapy techniques deliver a very high dose, of the order of 1.6-5.0 Gy/min, so mistakes can lead to under- or overdosage with the potential for clinical adverse effects. More than 500 HDR accidents (including one death) have been reported along the entire chain of procedures from source packing to delivery of dose. Human error has been the prime cause of radiation events. In the present report, the International Commission on Radiological Protection concludes that many accidents could have been prevented if staff had had functional monitoring equipment and paid attention to the results. Since iridium has relatively short half-life, the HDR sources need to be replaced approximately every 4 months. Over 10,000 HDR sources are transported annually, with the resultant potential for accidents; therefore, appropriate procedures and regulations must be observed. A number of specific recommendations on procedures and equipment are given in this report. The need for an emergency plan and for practising emergency procedures is stressed. The possibility of loss or theft of sources must be kept in mind. A collaborating team of specifically trained personnel following quality assurance (QA) procedures is necessary to prevent accidents. Maintenance is indispensable component of QA; external audits of procedures re-enforce good and safe practice, and identify potential causes of accidents. QA should include peer review of cases. Accidents and incidents should be reported and the lessons learned should be shared with other users to prevent similar mistakes.