[en] In the frame of FP7_-NEWLANCER project, SWOT analysis (Strengths, Weaknesses, Opportunities and Threats) was performed by each partner from New Member States (NMS) in order to provide valuable input for the development of policies aimed to increase the participation of the NMS in Euratom programmes on the following topics: Generation III and IV systems and materials, Nuclear safety, Radioprotection, Radioactive waste management, and Education and training. The final objective of SWOT analysis performed by National Expert Groups on Nuclear Safety (NS) topic was to propose strategies, in order to reduce the influence of identified negative factors and to enhance influence of identified positive factors, regarding Romanian participation in Euratom programmes. (authors)

[en] The proceedings of the NUCLEAR 2013 international conference on sustainable development through nuclear research and education held at INR-Pitesti on May, 22-24 2013 contain 79 communications presented in two plenary sessions. The sections of conferecnce are adressing the following items: Section I.1 Nuclear Safety & Severe Accidents (15 papers), Section I.2 Nuclear Reactors & Generation IV (15 papers), Section I.3 Nuclear Technologies & Materials (28 papers), Section II.1 Radioprotection (6 papers), Section II.2 Radioactive Waste Management (8 papers), Section II.3 Air, Water & Soil Protection (5 papers) and Section III Sustainable Development (4 papers) These papers are presented as abstracts in 'Nuclear 2013 - BOOK of ABSTRACTS', separately processed

[en] The measurement of radioactivity concentrations in soil is an important tool for the monitoring of the environment. For this purpose, within our laboratory has been implemented a radiochemical procedure for the determination of alpha-emitting isotopes of uranium, plutonium and americium in soil samples. The main steps of the procedure include leaching and dissolution of the sample, separation by extraction chromatography, source preparation and alpha-spectrometry. The analysis of environmental samples for low levels of U, Pu, Am and other actinide elements is often hampered by sample-dependent problems involving the composition and/or mineralogy of specific samples. While relatively small samples (1-2 g of soil) are required to reach the extremely low detection limits occasionally mandated for environmental monitoring. "2"3"2U, "2"4"2Pu and "2"4"3Am were added to the sample for chemical yield monitoring and to correct the results and to improve precision. Actinides are separated and purified by extraction chromatography with UTEVA and TRU resin, co-precipitated with cerium fluoride, filtered, and counted by alpha-particle spectrometry. The separation yields for the analyses were determined following each separation step and the global separation yields were determined for the entire analytical process. Results show a chemical yield of 90% for uranium, 30% for plutonium and 70% for americium. Also, the activity values obtained for these samples were comparable with the reference material values. (authors)

[en] The paper presents the results obtained from the implementation of the "3H and "1"4C measurement methods on the TriCarb "3"1"1"0TR using Normal Count Mode (typical count rate > 500CPM). Two types of organic solutions were used: "3H in toluene, with activity of 44886.51dpm/ml and "1"4C SPEC-CHEC solution with activity of 929000dpm/ml. To determinate counting efficiency and calculate DPM (Disintegrations Per Minute), quench curves must be performed for each radionuclide. These curves are obtained using a quench standards set, each containing the same amount of nuclide with varying amounts of quenching agent. The high values obtained by both methods for efficiency recovery of "3H and "1"4C indicate very good measurement efficiency (for tritium in the range 0-18.6keV, the minimum acceptable efficiency is 60% while for carbon-14 in the range 0-156keV, the minimum acceptable efficiency is 95%). (authors)

[en] This paper presents the experimental tests of a chlorine separation and purification method from aqueous samples with knowing content of Co, Cs, Eu, Ni and Sr stable elements. The method is based on the property of chloride ions to form a silver chloride white precipitate, followed by the use of the extraction chromatography on the strong anionic resin (Bio-Rad AG® 1-X_4) to purify chlorine. The concentrations of Co, Cs, Eu, Ni and Sr (separated from Cl by using precipitation method) were measured by ICP-OES. The silver chloride precipitate was dissolved in 25 % NH_3 solution and loaded onto the anionic resin. The chloride ions were strongly retained on the resin and eluted with a proper solution. The final solution, containing chloride ions, was converted to a form compatible with the spectrophotometric and Mohr titration techniques, which were used to determine chloride concentration. The separation yields of Co, Cs, Eu, Ni and Sr from Cl are very good. More than 98 % from the initial concentration of chlorine was recovered. (authors)

[en] The paper presents a study of the treatment techniques used for uranium recovery from aqueous solutions, such as: precipitation, ion exchange processes, sorption processes, solvent extractions, separation by liquid membrane, nanofiltration and reverse osmosis. The necessary elements for rigorous treatment experiments that can be used to define innovative procedure for uranium contaminated wastewater treatment are described in this review. The published data were summarized and the areas for further research were identified in order to be able to propose an environmental friendly technology in the field of uranium production and recovery cycle. (authors)

[en] The procedure for determination of uranium content in aerosol filters by alpha spectrometry is an appropriate method of monitoring the releases in the environment. The procedure is based on the use of UTEVA resin to separate the uranium. For sample preparation, the filter is dissolved with concentrated nitric acid and hydrogen peroxide, at boiling temperature. Separation yield of actinides is monitored with addition of a known amount of "2"3"3U tracer, to the initial sample. Source preparation for alpha spectrometry is performed by micro-precipitation with cerium fluoride. The sample is filtered by using a 0,1 micron 25 mm filter, followed by the mount on stainless steel plate, for subsequent counting by alpha-spectrometry. The separation yields for the analytes were compared, as concerns the recoveries and the counting efficiencies, with used reference materials. (authors)

[en] The European Network on Neutron Techniques Standardization for Structural Integrity (NeT) was established in 2002, grouping institutions from industry, research and academic media. Coordinated by the European Commission.s Joint Research Centre, the main mission of this network is to develop experimental and numerical techniques and standards for the reliable characterisation of residual stresses in structural welds. Each problem is tackled by creating a dedicated Task Group which manages measurement and modelling round robin studies and undertakes a thorough analysis and interpretation of the results. Over forty institutions are active NeT partners, their specific involvement and contributions being summarised in this paper. The Institute for Nuclear Research Pitesti (INR) is one of NeT founders and its contribution is related to numerical modelling, specimen analysis, material characterisation, data analysis or SANS support. This is also emphasised throughout this paper, together with the specific NeT research topics presentation. (authors)

[en] The competence of laboratories is assessed by two complementary techniques. One of the techniques is the on-site evaluation following the requirements of ISO/IEC 17025:2005. The other one implies the proficiency testing which involves the determination of laboratory performance by means of interlaboratory comparisons, whereby the laboratory performs practical tests and their results are further compared with those of other laboratories. The paper treats one of the most important topics of the proficiency testing – the interlaboratory comparison (ILC). There will be presented the need, the purpose and the main objectives of an ILC and also a typically situation where an interlaboratory comparison exercise (for radio-analytical methods) was planned. A fully description of the design and operation of an ILC scheme is the main purpose of this paper. A special attention will be given to the data analysis and evaluation of interlaboratory comparison scheme results. (authors)

[en] The present paper presents a study, by thermal analysis, of the hydration of a mixed binder system consist of Portland composite cement type CEM II/A-M(S-LL) 32,5 R and calcium aluminate cement type GORKAL 70, patented by the authors for embedding spent radioactive solvents. Cement hydration reactions are often affected by the presence of a spent radioactive solvent, usually retarded. This process can be monitored by thermal analysis and often quantified. The data are being used as a reference to compare the changes in the cement blend hydration during the solidification caused by the presence of the spent radioactive solvents itself or by emulsifier additives which are being availed. Detailed analysis of DTG (derivative thermo gravimetric) decomposition profiles of portlandite and carbonate enabled the evaluation of admixture-related parameters concerning portlandite formation and also indicated the behaviour of specific carbonates during the hydration process. (authors)