[en] Carbon-14 is a long lived radionuclide (half life of 5730 years) present in almost all radioactive waste streams generated by a CANDU nuclear power plant. It is a pure beta emitter that decays to 14N by emitting low energy beta-radiation with an average energy of 49.5keV and a maximum energy of 156keV. Before the beta radiation of 14C can be measured from radioactive waste liquid scintillation counting (LSC), the samples must be transformed in a stable, clear and homogeneous solution. Two methods were tested for carbon-14 recovery and analysis in radioactive wastes from nuclear power plants. The combustion process is a simple automatic method of sample preparation, in which all carbon isotopes, including 14C are oxidized to gaseous carbon dioxide that is subsequently trapped in form of carbonate in a column filled with a carbon dioxide absorbent. The microwave digestion is the method wherein the samples are transformed totally or partially in liquid phase depending on the sample matrix using adequate digestion reagents. The samples were counted with a normal and low level count mode liquid scintillation counter Tri-Carb3110TR. The tests performed on the simulated radwaste showed a 14C recovery of 90% by combustion and higher than 75% by microwave digestion method. (authors)

[en] The risks related to the implementation of ALFRED demonstrator in Romania are discussed. The assessment is based on the risk matrix approach. Two groups of experts were used in the investigation: participants in FP7 ARCADIA projects and members of the FALCON consortium. The results consist of the hierarchy of the risks obtained based on the appreciations of the two groups. They are comparatively presented and discussed in terms of the identified critical risks and possible measures for prevention and mitigation. Additionally, some elements derived from the experience of similar project such as SUSEN and ELI-NP are discussed. (authors)

[en] The paper presents the way to implement a Fuel Handling System (FHS) data base in order to carry out an informatic system for training, examination and knowledge evaluation. The sessions, are organized as ''ebooks'' represent a way of modern learning and thoroughness, examination and assessment of the professional knowledge. The use of these lessons for personnel training, working in the FHS area, leads both to the increase of the learning quality and reduction of the time for studying activities. The student is getting the advanced professional knowledge regarding the technological equipment operation by graduating the session. This e-learning system is designed and used to keep and develop, in time, deep in knowledge, about Fuelling Machine Head construction and working, for F/M Test Rig operators and technicians, from INR Pite.ti. The e-lessons for F/M snout clamp, magazine and separators have been already implemented, the rest of materials in data base is following. (authors)

[en] Modern methods and technologies coupled together with advanced equipment for treating residual substances resulted from technological processes are mandatory measures for all industrial facilities. The correct management of the used working agents and of the all wastes resulted from the different technological process (preparation, use, collection, neutralization, discharge) is intended to reduce up to removal of their potential negative impact on the environment. The high pressure and temperature testing stands from INR intended for functional testing of nuclear components (fuel bundles, fuelling machines, etc.) were included in these measures since the use of oils, demineralized water chemically treated, greases, etc. This paper is focused on the method and equipment used at INR Pitesti in the chemical treatment of demineralized waters, as well as the equipment for collecting, neutralizing and discharging them after use. (authors)

[en] The paper presents the testing methodology on the CANDU pressure tube specimens (Zr-2.5% Nb alloy) to determinate the fracture mechanics parameters. The crack initiation and subsequent DHC propagation tests were performed on compact-tension (CT) specimens prepared from pressure tube off-cuts. Previously, the CT specimens were subjected to the specific method to increase the hydrogen concentration up to 50 ppm. This process consists of two stages: the first one is the electrolytic disposal of a uniform zirconium hydride layer and, the second one is to apply a homogenization thermal treatment causing the diffusion of hydrogen into the zirconium matrix from the hydride surface layer. The testing temperature was around 280oC, which is the temperature of interest for the pressure tubes operating in CANDU 6 reactor. (authors)

[en] The human reliability assessment tools are not currently capable to model adequately the human ability to adapt, to innovate and to manage under extreme situations. The paper presents the results obtained by ICN PSA team in the frame of FP7 Advanced Safety Assessment Methodologies: extended PSA (ASAMPSA_E) project regarding the investigation of conducting HRA in human-made hazards. The paper proposes to use a 4-steps methodology for the assessment of human interactions in the external events (Definition and modelling of human interactions; Quantification of human failure events; Recovery analysis; Review). The most relevant factors with respect to HRA for man-made hazards (response execution complexity; existence of procedures with respect to the scenario in question; time available for action; timing of cues; accessibility of equipment; harsh environmental conditions) are presented and discussed thoroughly. The challenges identified in relation to man-made hazards HRA are highlighted. (authors)

[en] Management of radioactive waste is an integral and very important part of 99Mo production, especially for fission 99Mo, and should be given high priority during production process development and operation. To ensure a continued reliable and cost-effective supply of 99Mo, the management of associated waste must be carried out in accordance with internationally accepted safety criteria and related national regulations. The waste products form and characteristics will be dependent on the process design and chemistry. Typically, vital aspect of the Fission Production Mo processing is the holding of waste streams at the site of production for initial decay of the shorter lived fission products. This usually follows a sequence of in-cell storage, storage adjacent to the hot cell operations, and transfer to longer term storage or processing. Adequate capacity must be allowed for this initial waste storage at the hot cell area. (authors)

[en] The purpose of this paper is to determine the chemical elements concentrations which affect both the population health and environment, such as toxic agents which are contained in air and are retained by precipitation inside the biomonitors vegetal tissues. The Neutron Activation Analysis is an analytic technique based on measuring the numbers and the energy of gamma radiation emitted by the radioactive isotopes produced in the sample matrix by irradiation with thermal neutrons in a nuclear reactor [1]. Usually, the samples are irradiated together with specific neutron flux monitors, duplicates and interest elements standards for a prior selected period of time inside the core of nuclear reactor. After the irradiation experiment and the specific radioactive decaying, can proceed measuring the gamma energies spectrum by using a high resolution detection system (HPGe - High Purity Germanium crystal) for gamma spectrometry and then assess the impact of the traced elements on population and environment. (authors)

[en] The paper focuses on evaluating the depositions and support materials used in radiation detectors, by microstructure characterization techniques. Boron depositions on aluminium surface and colloidal graphite deposition on polyethylene support were experimentally obtained. Advanced examination techniques, such as Scanning Electron Microscopy (SEM) and Energy Dispersive X-Ray Spectrometry (EDS) were used for investigations. Because boron cannot be detected by EDS, its deposition was investigated using backscattered electron signals in SEM. The adherence, compactness, chemical composition and content of impurities are the main characteristics of graphite deposition used in radiation detectors. In order to obtain an accurate detection for all deposition types, the impurities content from the depositions has to be small. As result, the examined boron deposition, which was not dense, presented un-connected, non-adherent crystals with different shapes and sizes. The graphite deposition has proven to be adherent, continuous, compact, but not uniform in terms of thickness. (authors)

[en] CORONA Project is established to stimulate the transnational mobility and lifelong learning amongst VVER end users. The project aims to provide a special purpose structure for training of specialists and to maintain the nuclear expertise by gathering the existing and generating new knowledge in the VVER area. CORONA Project consists of two parts: CORONA I (2011-2014) ''Establishment of a regional center of competence for VVER technology and Nuclear Applications'', co-financed by the Framework Program 7 of the European Union (EU) and CORONA II (2015-2018) ''Enhancement of training capabilities in VVER technology through establishment of VVER training academy'', co-financed by HORIZON 2020, EURATOM 2014-2015. The selected form of the CORONA Academy, together with the online availability of the training opportunities will allow trainees from different locations to access the needed knowledge on demand. The project will target also new-comers in VVER community like Vietnam, Turkey, Belarus, etc. (authors)