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  1. Reactor safety

    The EU is concerned with ensuring that the highest standards of reactor safety are adopted and maintained. The Council Directive 2009/71/EURATOM establishing a Community framework for the nuclear safety of nuclear installations stipulates the application ...

    30 April 2014

  2. Analysis of the Thermal Fatigue Cracking of 316L Model Pipe Components under Cyclic Down-Shocks

    Cylindrical test pieces of low-carbon austenitic steel 316L are subjected to cyclic thermal loads in a specially designed rig. Intermittent stops allowed measurement of cycles to initiation and of the propagation of the networks of axial and circumferenti ...

    30 April 2014

  3. Design of a Rotating Facility for Extra-Corporal Treatment of an Explanted Liver with Disseminated Metastases by BNCT with an Epithermal Neutron Beam

    In 2001, at the TRIGA reactor of the University of Pavia (Italy), a patient suffering from diffuse liver metastases was successfully treated by BNCT. This encouraging outcome stimulated the Essen/Petten BNCT-group to investigate whether such an extra-corp ...

    30 April 2014

  4. CFD Modelling of Accidental Hydrogen Release from Pipelines

    Although today hydrogen is distributed mainly by trailers, in the long terms pipeline distribution will be more suitable if large amounts of hydrogen are produced on industrial scale. Therefore from the safety point of view it is essential to compare hydr ...

    30 April 2014

  5. Overview of EC Activities on Environmental Remediation in CIS Countries under TACIS Programme

    This paper describes the direct experience of the authors in defining, contracting and monitoring projects in the area of TACIS Nuclear Safety encompassing Environmental and Radioactive Waste Management. It describes projects dealing with Chernobyl NPP, S ...

    30 April 2014

  6. Effect of Irradiation Temperature in PWR RPV Materials and its Inclusion in Semi-Mechanistic Model

    The irradiation temperature is a very important parameter in radiation damage kinetics. In this article the challenge of including temperature into a general semi-mechanistic model for radiation embrittlement is presented. In this manner the model allows ...

    30 April 2014

  7. European Expert Network for the Reduction of Uncertainties in Severe Accident Safety Issues (EURSAFE)

    EURSAFE thematic network was a concerted action in the 6th Framework Programme of the European Commission. It established a large consensus among the main actors in Nuclear Safety on the Severe Accident issues where large uncertainties still subsist. As t ...

    30 April 2014

  8. Thematic Network for a Phebus FPT1 International Standard Problem (THENPHEBISP)

    The THENPHEBISP 2-year thematic network was concerned with the OECD/CSNI International Standard Problem No. 46, iteself based on Phebus FPT1 core degradation/source term experiment. The main aim was to assess the capability of computer codes to model in a ...

    30 April 2014

  9. SMILE: Validation of the Warm-Pre-Stress Effect with a Cylindrical Thick-Walled Specimen

    The assessment of defects in reactor pressure vessel subjected to pressurized thermal shock (PTS) transients do not necessarily consider the beneficial effect of the load history (warm pre-stress, WPS).The SMILE project performed a PTS type transient expe ...

    30 April 2014

  10. Core Loss During a Severe Accident (COLOSS)

    The core loss during a severe accident (COLOSS) project was a 3-year shared-cost action, which started in February 2000. The project is concerned with the consequences that core degradation, occurring under severe accident conditions, may have on H2 produ ...

    30 April 2014

  11. Input Parameters Distribution Sensitivity Study of RBMK-1500 Reactor One Group Distribution Header Complete Blockage Scenario

    The paper presents sensitivity and uncertainty study of Ignalina NPP RBMK-1500 reactor one group distribution header complete blockage accident scenario. The uncertainty analysis includes determination of major input variables contributing to output uncer ...

    30 April 2014

  12. Overview of ASTEC Topic After 19 Months

    An overview of the results achieved in the SARNET (Severe Accident Research and management NETwork) Work-Packages "Users’ Support, Training, Integration and Adaptation", "Reactor Application and Benchmarking", benchmarks on and "P ...

    30 April 2014

  13. Factors Limiting the In-Service Lifetime of CrMoV Steels and Weldments for Pressure Equipment

    The combined effect of both creep and hydrogen attack is the object of this study. This is the cause of damage and catastrophic failures of industrial copmonents, with huge economic impact on the affected plants. Tests representative of the industrial rea ...

    30 April 2014

  14. Research and Standardization Activities on Neutron Methods at HFR Petten

    Thermal and sub-thermal neutrons are invaluable tools for investigations in fundamental, engineering and medical science. Most neutron applications are non-destructive, as neutrons penetrate deeply into most materials. In the engineering field, neutrons a ...

    30 April 2014

  15. Integral Large Scale Experiments on Hydrogen Combustion for Severe Accident Code Validation- HYCOM

    A joint research project was carried out in the EU 5th Framework Programme, concerning hydrogen risk in a nuclear power plant. The goals were: Firstly, to create a new data base of results on hydrogen combustion experiments in the slow to turbulent combus ...

    30 April 2014

  16. Ancillary Tools to Help Experts Providing Opinions- Application Examples in Nuclear Safety Issues

    The idea behind this work is the need to design training sessions for the experts to let them to get the maximum bene3fit from their knowledge and the information they can get from their computer codes. Those tools hsould be made available to the expert b ...

    30 April 2014

  17. Validation of Severe Accident Codes on the Phebus Fission Product Tests in the Framework of the PHEBEN-2 Project

    Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order to develop accident management strategies that prevent such acci- dents or mitigate their consequences for the environ- ment. The most important requiremen ...

    30 April 2014

  18. Towards Harmonised Self Assessment of Research Reactor Safety Status in Operating Organisations

    Objective is to describe the development of a methodology and web-based tool for mapping and cross-comparing safety approaches in European and other Research Reactor (RR) facilities to detect principal similarities and differences. Information for RRs fro ...

    30 April 2014

  19. Hydrodynamic Analysis and Design of High-Level Radioactive Waste Disposal Model Penetrators

    Abstract not available VISINTINI Livio, MARAZZI R. 1990 EUR- Scientific and Technical Research Reports Joint Research Centre Corporate Activities Nuclear safety and security nuclear, reactor, water, waste, modelling Corporate, IET CEC EUR 12780 EN ...

    30 April 2014

  20. Lattice Location of Oxygen Atoms in UO2 Single Crystals Leached in Water.

    The effects of aqueous oxidation of (100)-oriented UO2 single crystals have been studied by means of the RBS/channeling technique. The) sublattice is analysed by using the 160(4He,4He)160 resonance at 3045 keV. A strong flux-peaking effect is observed in ...

    30 April 2014

  21. European Clearinghouse- Incidents Related to Reactivity Management- Contributing Factors, Failure Modes and Corrective Actions

    This work is part of the European Clearinghouse on Nuclear Power Plant Operational Experience Feedback (NPP-OEF) activity carried out at the Joint Research Centre/Institute for Energy (JRC/IE) with the participation of nine EU Regulatory Authorities. It i ...

    30 April 2014

  22. Lessons learnt from a crisis event: How to foster a sound safety culture

    Recent events in the nuclear industry have blamed a declining safety culture both on the utility and regulatory side as the major responsible. Confidence in the nuclear industry can be dramatically affected by such events. In this context, the present pap ...

    30 April 2014

  23. Some considerations on the role of LSD spikes in safeguarding nuclear reprocessing plants

    Large sized dried spikes (LSD) are a fundamental part of the fissile material control of irradiated nuclear fuel. They are applied to measure the uranium and plutonium content of dissolved fuel solutions from reprocessing plants using isotope dilution mas ...

    30 April 2014

  24. Current Practices for Risk Zoning Around Nuclear Power Plants in Comparison to Other Industry Sectors

    This paper analyses the background and current status of the information basis leading to the definition of risk and emergency zones around nuclear power plants (NPPs) in different countries in Europe and beyond. Although dependable plant-specific probabi ...

    30 April 2014

  25. Understanding the Complex Phase Diagram of Uranium- the Role of the 5f States

    Predictions of the phonon behaviour at high pressure are included in the recent first-principle calculation of the phonons in uranium. Experiments up to 20 GPa using inelastic x-ray scattering confirm these predictions. Extending the theory explains the c ...

    30 April 2014