Search

How to create queries in the free text search:

  • Add double quotes around a group of words to search for pages containing that group (e.g. "fuel cells")
  • AND (or &&):  wind AND "solar panels" returns pages containing both "wind" and "solar panels".
  • OR (or a space): wind "solar panels" returns pages containing wind or "solar panels".
  • NOT (or !): solar NOT "solar panels" returns pages containing solar but not "solar panels".
  • Use the various filters (left column) to refine or reset your search.
  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. Grain-Scale Modeling Approaches for Polycrystalline Aggregates

    JRC article presenting some of the most often used approaches to modeling polycrystalline aggregates, starting from more simplistic approaches and up to the most state-of-the art approaches that draw on the as-measured properties of the microstructure. In ...

    30 April 2014

  3. Thermal properties of irradiated UO2 and MOX fuels

    Article presenting the phenomena causing the degradation of the thermal conductivity of UO2 and MOX LWR fuels as a result of reactor burn-up. The thermal conductivity of UO2 and MOX LWR fuels decreases as a result of reactor burn-up. In this chapter, the ...

    30 April 2014

  4. Interpretation and Use of the Results of Proliferation Resistance Studies

    JRC article identifying a reference set of decision makers and other users who could be informed by the results of proliferation resistance assessments. It examines the information needs of different classes of decision makers, and presents ideas on how t ...

    30 April 2014

  5. Depletion analysis of the HELIOS experiment using the MCB code

    Article presenting an advanced depletion analysis of the HELIOS experiment by means of the Monte Carlo continuous energy burn-up code (MCB). The focus of our studies is to present an advanced depletion analysis of the HELIOS experiment by means of the Mon ...

    30 April 2014

  6. Spent Nuclear Fuel as Waste Material

    Article dealing with spent light water reactor fuel, mainly UO 2 and mixed oxide fuel, in respect to its change of the chemical and mechanical properties during long-time storage in a deep underground repository. In general this chapter deals with spent L ...

    30 April 2014

  7. Spent Fuel Dissolution and Reprocessing Processes

    Article discussing the development of reprocessing technologies of the fuel powering different generations of nuclear reactors. The initial motivation for the development of reprocessing technologies was to obtain pure fissile material for nuclear weapon ...

    30 April 2014

  8. 3.4. Research and Development of Thorium in Nuclear Fuel-European Commission

    Article presenting results of neutronic assessments of the use of thorium fuel in current commercial PWR without modification of core and assembly characteristics performed within an INPRO thorium fuel cycles (ThFC) study. Thorium fuel cycles (ThFCs) have ...

    30 April 2014

  9. Calorimetric Study of Glass Structure Modification Induced by alpha Decay

    Article describing a calorimetric study of glass structure modification induced by alpha decay. R7T7-type glass samples doped with different concentrations of 244Cm and stored for different time periods to produce different levels of accumulated radiation ...

    30 April 2014

  10. Prompt gamma-ray energy in the frame of prompt neutron emission models

    A JRC contribution to a conference- the work  refers to the unique experimental data of prompt gamma-ray energy as a function of fragment measured for U-235(nth,f), very well described by the Point by Point model results obtained by using two methods of t ...

    30 April 2014

  11. Preparation of high resolution 238U alpha-sources by electrodeposition from aqueous solution

    JRC Scientific and Technical Research Report detailing the preparation procedure for high-resolution 238U sources. The source preparation procedure for high-resolution 238U sources is described in this work. For preparing alpha sources for high-resolution ...

    30 April 2014

  12. Matter Transport in Fast Reactor Fuels

    JRC article reviewing transport phenomena occurring in fast reactors, with a view to restructuring the fuel matrix and redistribution of its constituents. A comprehensive review of matter transport phenomena occurring in fast reactors is presented in term ...

    30 April 2014

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  21. 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

  22. 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

  23. 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

  24. 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

  25. 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