Results 1 - 10 of 65
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[en] Water, the most important and indispensable resource for life support is threatened. The whole world is worried about that, so, it is now learning, that there are limits to egregious waste, and is leading too his research and technical efforts to preserve the resource. This work suggest, as a part of these complementary efforts, the use of nuclear techniques: PIXE and X RF, adjusting to easier and faster analytical tools, for heavy metals content in water determinations, such techniques have a wide spread over safe water quality control. (Author)
[en] In Eastern Europe, people associate nuclear energy to the idea of progress, and prestige of the nuclear industry is very high. This article sets the use of nuclear technology to produce energy in a historical context that is particular to these countries. Results of interviews and surveys are analyzed in order to provide an insight on the level of acceptance among population. (Author)
[en] The objective of this project will be a model of containment PWR-W with the GOTHIC code that allows analyzing the behavior detailed after a design basis accident or a severe accident. Unlike the models normally used in codes of this type, the analysis will take place using a three-dimensional model of the containment, being this much more accurate.
[en] The GOTHICTM computer code is a state-of-the art program for modeling multiphase, multicomponent fluid flow. GOTHIC is rapidly becoming the industry-standard code for performing both containment design basis accident (DBA) analyses and analyses to support equipment qualification. GOTHIC has a flexible nodding structure that allows both lumped parameter and 3-D modeling capabilities. Multidimensional analysis capabilities greatly enhance the study of noncondensable gases and stratification and permit the calculation of flow field details within any given volume.
[en] The ENEN-III European project covers the structuring, organization, coordination and implementation of training schemes in cooperation with local, national and international training organizations, to provide training to professionals active in nuclear organizations or their contractors and sub-contractors. The training schemes provide a portfolio of courses, training sessions, seminars, and workshops for continuous learning for upgrading knowledge and developing skills.
[en] The main result of this paper is the proposal for the addition of new ingredients in the safety analysis methodologies for Generation-IV reactors that integrates the features of probabilistic safety analysis within deterministic. This ensures a higher degree of integration between the classical deterministic and probabilistic methodologies.
[en] Nuclear technology, developed over fifty years of knowledge, comprises many disciplines such as mechanical engineering, nuclear physics, automation, etc. During the operational experience of current reactors has developed a great knowledge that needs to be managed properly so present and future generations can enjoy this technology.
[en] The Thermo-hydraulic code GOTHIC is often used in the nuclear industry for licensing transient analysis inside containment of generation II (PWR, BWR) plants as Gen III and III + (AP1000, ESBWR, APWR). After entering the mass and energy released to the containment, previously calculated by other codes (basis, TRACE), GOTHIC allows to calculate in detail the evolution of basic parameters in the containment.
[en] The evaluation of Passive Autocatalytic Recombiner (PAR) implementation has been developed under the methodology extracted from the IAEA document, analysing the size, location and number of the PARs capable to minimize the combustion risk, which arises from a hydrogen release generated during a severe accident and its distribution in containment building. A detailed three-dimensional model of Konvoi (PWR) containment with GOTHIC 8.1 code was used for the simulations. The hydrogen preferential pathways and the accumulation points were studied and identified on the basis of a base case scenario without any mitigation measure. The PAR configuration offers an improvement in the chosen accidental scenario; decreasing the possibility of hydrogen combustion and leading to concentration values below the flammability limit (hydrogen concentration below 7%), in all the containment compartments at the end of the transient. Furthermore, from the analysis, it is concluded that the time required to reach hydrogen concentrations below the combustion limit is considerably reduced. (Author)
[en] The type SGTR accident is a case of loss of coolant accident small features which make it necessary to differentiate and evolution of classical studies LOCA sequence type. To simulate this type of accident has chosen the MELCOR code, which aims to study the progression of severe accidents in LWR plants. It has been developed by Sandia National Laboratories for the United States Nuclear Regulatory Commission.