[en] As a consequece of the incident of the smelting sources of Cs-137 in steel mills, there have been generated radioactive waste a few different iron which habitually they are produced in the nuclear facilities operation, which has needed the adjustment of some facilities of the C. A. El Cabril and the implantation of new equipments and systems. (Author)

[en] Shallow geothermal energy application in buildings and civil engineering works (tunnels, diaphragm walls, bridge decks, roads, and train/metro stations) are spreading rapidly all around the world. the dual role of these energy geostructures makes their design challenging and more complex with respect to conventional projects. Besides the geotechnical parameters, thermal behavior parameters are needed in the design and dimensioning to warrantee the thermo-mechanical stability of the geothermal structural element. As for obtaining any soil thermal parameter, both in situ and laboratory methods can be used. The present study focuses on a lab test known the need ke method to measure the thermal conductivity of soils (λ). Through this research work, different variables inherent to the test procedure, as well as external factors that may have an impact on thermal conductivity measurements were studied. Samples extracted from the cores obtained from a geothermal drilling conducted on the campus of the Polytechnic University of Valencia, showing different mineralogical and nature composition (granular and clayey) were studied different (moisture and density) compacting conditions. 550 thermal conductivity measurements were performed, from which the influence of factors such as the degree of saturation-moisture, dry density and type of material was verified. Finally, a stratigraphic profile with thermal conductivities ranges of each geologic level was drawn, considering the degree of saturation ranges evaluated in lab tests, in order to be compared and related to thermal response test, currently in progress. Finally, a test protocol is set and proposed, for both remolded and undisturbed samples, under different saturation conditions. Together with this test protocol, a set of recommendations regarding the configuration of the measuring equipment, treatment of samples and other variables, are posed in order to reduce errors in the final results. (Author)

[en] The objective of this book is to prepare and to arrange the information related to tritium and radioprotection, as well as its influence on human beings and the environment. Physical, chemical, biological and radiological properties of tritium are analyzed and the basic detection and measurement methods are discussed. Production procedures and the main applications of tritium are described. To study in depth quantitative aspects, 50 examples, fully solved, about radioactivity or dose are included. Finally, risk analysis and radioprotection procedures used in two specific plants are described. (Author) 77 refs

[en] In this work, the most relevant results of a research project on the mechanical and fracture behavior of cladding in transport and dry storage conditions are summarized. the project is being carried out at Universidad Politecnica de Madrid in collaboration with ENUSA, ENRESA and CSN. Non-irradiated cladding is investigated. The main objective is to determine a failure criterion of cladding as a function of hydrogen content, temperature and strain rate. (Author)

[en] In this paper, the experimental techniques employed to reproduce in the laboratory the distribution, morphology and orientation of the hydrides during the different steps of the nuclear fuel cycle are reported. A cathodic charging technique was employed to produce ZIRLO cladding samples with an homogeneous distribution of hydrides and concentrations of 150, 250, 500, 1200 and 2000 ppm of hydrogen. The treatments developed to produce radial hydride reorientation, hydride blisters and a peripheral rim of hydrides are described.

[en] The performance of Probabilistic Safety Analyses (PSA) at Trillo 1 NPP is facing a number of challenges, unprecedented in previous PSAs carried out in Spain, due to the particular design characteristics of the plant. On account of this, it has been necessary to implemented specific approaches and methodological alternatives to perform a PSA which, while maintaining detail level and requirements in line with PSAs carried out previously in Spain, offers a solution technically adapted to the characteristics of the SIEMENS-KWU design as opposed to other Spanish reactors with a basic Westinghouse-General Electric design, which are based on standard US design. The purpose of this paper is to describe the most significant characteristics of the PSA at Trillo 1 NPP and the methodology used to date, taking into account current project progress

[en] As a starting point, samples were taken at different concentrations of hydrogen, 150, 500 and 1200 ppm. Hydrogen therein was precipitated as hydrides homogeneously distributed in circumferential cross section of the cladding. These samples were subjected to thermomechanical processes representative of dry storage.

[en] Considering the quasi-molecular approximation, Jahn-Teller distortions are calculated for the regular and the distorted octahedra with apical oxygens, using structural data experimentally obtained for both the CuO6 and NiO6 clusters. The Jahn-Teller effect is discussed in the superconducting and non-superconducting materials in order to find its possible relevance to the superconducting mechanism as it was first suggested by Bednorz and Mueller

[en] In July 1991, C. N. Trillo I was requested by the Spanish Regulatory Body (CSN) to perform a PSA that should include: - Level 1 PSA at power - Internal flooding analysis - Level 2 PSA including containment capacity analysis. - External event analyses (fires, external flooding, seismic events and other external events) - Risk analysis for off power conditions (shutdown and low power) - Risk analysis due to other sources of radioactivity In 1992 the Project Plan was issued and the PSA team for the performance of Level 1 PSA was established. Before finishing the Project, it was decided to develop a Phase B to take into account some important modifications that had been accomplished in the Plant and that, probably, could affect the results. Level 1 PSA was finished in March 1998. Both the results of the study and the main conclusions derived from the importance, uncertainty and sensibility analysis performed are presented in this paper. These results de not include the internal flooding analysis conclusions and correspond to PSA revision 0 that is currently being evaluated by the Spanish Regulatory Body. (Author)

[en] A matrix of eleven experiments on aerosol retention behaviour in submerged beds and suppression pools in water- cooled reactors under severe accident conditions has been performed, for these experiments, an intermediate scales, multi-purpose facility was set up at CIEMAT (Madrid). The facility includes various systems: aerosol generation (Csl), mixing section, injection line and pool-vessel (8 m³ ), as well as the corresponding aerosol instrumentation and a process control and data acquisition system. Some parameters have been varied in order to study their influence in the DF: steam/noncondensable ratio in the accidental mixture (0.1 to 0.9), particle size, flow rate (two regimes: bubble and jet) and injector geometry (mono orifice and multi orifice). On the other hand, some parameters have been kept constant along the experiments; pool geometry (diameter, water level), water temperature, pressure in the atmosphere above the water, submergence, injection temperature and injection time. A rapid decrease in the DF is observed as the proportion of particles measuring less than 1 μm increases. Retention decreases in the case of smaller particles and considerably higher in the case of larger particles. It has been also possible to observe the influence of the injected steam fraction. Experiments with greater fraction than the saturation fraction have greater DF than those ones with smaller fractions. The jet regime with horizontal injection and the multi orifice geometry would appear to show a somewhat higher capacity of retention than those in the bubble regime under similar conditions. It would be necessary to confirm this greater capacity for retention by means of additional experimental data. This work, performed by the LACE-Espana Consortium, has been carried out in the frame of the European Commissions Shared Cost Action Programme on Reactor Safety 1988-91 on a contractual basis. (Author)18 refs