[en] The FP7 ASAMPSA_E (Advanced Safety Assessment Methodologies: extended PSA) project aimed to promote good practices for the investigation of critical situations induced by the occurrences of external hazards and their combination, and to develop some technical recommendations for improvement of PSAs studies. The paper presents the work performed in the frame of the ASAMPSA_E work packages by the Institute for Nuclear Research (RATEN ICN) PSA team members, with specific focus on the activities to which they have contributed. The ways in which the End-Users were involved in the project and the modalities in which they have influenced the partner actions, directions for prioritization and progress of the project are also discussed. Some of the challenges and the recommendations of the project regarding the assessment of external hazards and their combinations are highlighted. (authors)

[en] Climate changes have been recognized to be one of the most challenging issue of the humanity. The goal of this paper is to evaluate different energy generation scenarios inside of the national Romanian energy sector targeting a sustainable reduction of greenhouse gases (GHG) emissions. Three scenarios of carbon dioxide (CO2) emissions reduction until 2050 were proposed: by 50%, 70% and 90% from the 2012 levels. As result, three National Determined Contribution (NDC) levels of CO2 emission avoiding have been calculated. The IAEA-MESSAGE (International Atomic Energy Agency Model for Energy Sustainable Strategy Alternatives and their General Environmental Impacts) computer tool was used to perform the analyses. The paper‘s results show that a sustainable reduction can be assured for the first two scenarios, with some minor gaps. The paper concludes that CO2 reduction levels larger by 70% of 2012 levels are not sustainable. (authors)

[en] Safety in transport of radioactive material is primarily ensured using the appropriate type of package in compliance with the requirements specified in the IAEA Transport Regulations which are generally consistent with the regulations for all modes of transport. For each design of package for the transport of radioactive material, it is necessary to demonstrate compliance with national and international regulations as applicable. It is recommended to combine all information necessary to demonstrate compliance in a package design safety report. This paper present the European Technical Guide applicable to all types of packages which propose a structure and a minimum content for the safety report to assist the applicant in order to demonstrate the compliance of packages with the regulations. The paper gives an overview of elements involved in the achievement of the safety report of radioactive transport packages in order to transfer the knowledge to the young generation. (authors)

[en] The paper performs an analysis of the relevant types of Legal Entities (LEs) under international, European and national laws. Seven selection criteria (SC) were defined to evaluate them for the purpose of ALFRED implementation in Romania. A scale with five levels was used to quantify the appreciations. Based on this evaluation, five potentials LEs were retained for the final discussion, in order to identify the optimal approach. A comparative analysis of these 5 LEs was achieved based on the judgement of their advantages and disadvantages. As the main result two LEs were recommended: International non-profit association (AISBL) and Romanian association. A more detailed discussion on the two LEs has considered the specific elements of ALFRED implementation such as the envisaged funding scheme based on a mix of public funds (European structural funds and national funds), the role of operator, and of the implementer. A non-profit association under the Romanian law was selected as the final recommendation. (authors)

[en] Determination of uranium content in aerosol filters is a part of the regular monitoring program for nuclear facilities. The monitoring of the atmospheric uranium releases, resulted from the incineration of uranium bearing waste, is done by the analysis of representative samples collected from the evacuation ducts of the installation. The monitoring method is based on the determination of the uranium content of the filters by alpha-spectrometry. The process consists of the following steps aimed to create the source for alpha spectrometry measurement: (1) dissolving of aerosol filters with concentrated nitric acid and hydrogen peroxide, (2) addition of a known amount of U tracer, (3) separation of uranium from other actinides using UTEVA resin, (4) precipitation with cerium fluoride and filtration using a 0.1 micron 25 mm filter. The validation of the method is based on the reference materials approach, by considering the recoveries and the counting efficiencies. (authors)

[en] The paper overviews the accomplishments of the project CORONA II. One of the tasks is to apply the activities towards implementation of ECVET. The pilot training was organised to test the methodologies and to monitor the effectiveness of the training scheme. The training evaluation was carried out by the assessment of the trainee‘s answers of the questionnaires and on the base of feedbacks from the participants. The key aspects that were observed were Organisation and management, Training materials, Use of laboratory equipment, Fulfilment of requirements for ECVET oriented training, Assessment of trainee‘s achievements, alignment with learning outcomes and overall course evaluation. It was validated that certain learning outcomes achieved by a learner correspond to specific outcomes which are required for a unit or a qualification. The results will be used for development of the criteria and the procedure for mutual recognition of curricula, courses and training sessions supporting the training. (authors)

[en] In this paper lattice and core neutronic calculations have been performed to find out the behaviour of a proposed Thorium-based nuclear fuel on relevant neutronic parameters as: the effective multiplication constant, discharge burnups, maximum channel and bundle powers, Coolant Void Reactivity (CVR). The standard 37-elements bundle along with the advanced RATEN ICN SEU43 bundle design have been used to carry out the nuclear fuel. The core calculations show that the 37-elements bundle design with Thorium-based fuel is a viable economical option, its discharge burnup being just a bit higher than that supplied by the SEU43 bundle one, when the same fuel density is used. In turn, the using of SEU43 bundle design revealed improvements in nuclear safety through a better flattening of the power distribution over the fuel rings. (authors)

[en] Zirconium chemical states have been assessed using X-ray photoelectron spectroscopy (XPS) measurements on Zy-4 fuel cladding tube hydrided at 96 ppm in order to explore the surface chemical modifications. In-depth chemical profiling reveals an increasing zirconium hydride content from 1.9% to 3.0% due to a decreased ubiquitous carbon surface contaminant. Additionally, the diminishing OH groups concentration was successfully associated with the decreasing ZrOx(OH)y chemical state content, from 98.1% to 76.7%, respectively, suggesting a depleted moisture amount with depth. Furthermore, by depth profiling the surface for 30s, the zirconium fully oxidized (ZrO2) was highlighted indicating the presence of the passivating oxide layer. (authors)

[en] The study has aimed the comparison of the processing efficiency for the direct conditioning by bituminization and for the treatment by Fenton oxidation of the spent radioactive ion exchange resins (SIER). Bituminized waste samples containing SIER were been manufactured. The laboratory-scale leaching tests for the radioactive contaminants of bituminized waste form were performed. The leaching behaviour depends on the physic-chemical property and the radioactive composition of the waste form. Fenton oxidation is an efficient method for the volume reduction and stabilization of the spent resins before further immobilization. The results showed that the spent resins could be effectively dissolved at pH < 1.5, [Fe2+] = 0.2 M and T 60°C. Therefore, the best volume reduction is expected to be obtained for the treatment by destructive methods while the direct conditioning shall be advantages from the point of view of safety and simplicity in operation, without significant investments for special equipment. (authors)

[en] The NUCLEAR 2017 international conference on sustainable development through nuclear research and education held at INR-Pitesti on 24-26 May, focussed and explored the following topics: I. Nuclear Energy: - Nuclear Safety and Severe Accidents; - Nuclear Reactors; - Nuclear Technologies and Materials. II. Environmental Protection: - Radioprotection; - Radioactive Waste Management; - Air, Water and Soil Protection. III. Sustainable Development: - Policies and Strategies in Energy and Nuclear Research; - Research Infrastructure; - Education, Training and Knowledge Management; - International Partnerships for a Sustainable Development. These papers are presented as abstracts in 'Nuclear 2017 - Book of Abstracts', separately processed.