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  1. Neutron data

    The JRC is by far the largest provider of neutron data in the European Union. The data is generated by measurements at its two large-scale particle accelerators, and is used for the safe operation of nuclear reactors, handling of nuclear waste and investi ...

    22 June 2015

  2. Measurement of 235U(n,n' gamma) and 235U(n,2n gamma) reaction cross sections

    The design of generation IV nuclear reactors and the studies of new fuel cycles require knowledge of the cross sections of various nuclear reactions. Our research is focused on (n, xn gamma) reactions occurring in these new reactors. The aim is to measure ...

    01 May 2013

  3. Fission Cross-Section Measurements of 233U, 245Cm and 241,243Am at CERN n_TOF Facility

    Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design o ...

    09 November 2011

  4. Database for Time-of-Flight Spectra Including Covariances

    A data format for time-of-flight spectra (transmission, reaction and self-indication yields) and their covariance matrices based on the AGS (Analysis of Geel Spectra) format is discussed in collaboration between EC-JRC IRMM and IAEA-NDS for the EXFOR libr ...

    09 November 2011

  5. Thin Tristearin Deposits as Solid Hydrogen-Rich Layers for Neutron Metrology

    Layers of solid material with a relatively high, constant content of hydrogen that is stable over al long period of timer are needed for recoil proton telecscopes and for precise determination of the cross section ratio of 235U(n,f)/H(n,n). Thin layers of ...

    09 November 2011

  6. A Transparent Detector for n_TOF Neutron Beam Monitoring

    In order to obtain high precision cross-section measurements using the time-of-flight technique, it is important to know with good accuracy the neutron fluence at the measuring station. The detector dedicated to these measurements should be placed upstrea ...

    09 November 2011

  7. Evaluation of Neutron Cross Sections for Hafnium in the Resolved Resonance Range

    The international High Priority Request list notes:- "In the nuclear industry hafnium is used as neutron absorbing material to regulate the fission process. Interpretation of critical experiments with UOx fuel conducted by CEA in the AZUR zero-power ...

    09 November 2011

  8. Magnetic and Electronic Properties of NpFeGa5

    NpFeGa5 single crystals prepared by the Ga-flux method have been investigated by magnetization, specific heat and 237Np Mössbauer spectroscopy measurements. An antiferromagnetic (AF) transition has been observed at TN ~ 114 K. The second AF transition whi ...

    12 November 2011

  9. Crystal Fields, Disorder and Antiferromagnetic Short-Range Order in Yb0.24Sn0.76Ru

    We report extensive measurements on a new compound (Yb0.24Ru0.76)Sn that crystallizes in the cubic CsCl structure. Valence band photoemission (PES) and L3 x-ray absorption show no divalent component in the 4f configuration of Yb. Inelastic neutron scatter ...

    12 November 2011

  10. Multipolar, Magnetic and Vibrational Lattice Dynamics in the Low Temperature Phase of Uranium Dioxide

    We report the results of inelastic neutron scattering experiments performed with triple-axis spectrometers to investigate the low-temperature collective dynamics in the ordered phase of uranium dioxide. The results are in excellent agreement with the pred ...

    17 April 2012

  11. 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 ...

    17 April 2012

  12. A methodfortheestimationoffissilemassbymeasuringthenumber of neutronsignalswithinaspecifictimeinterval

    The purpose of this paper is to present a new method for the estimation of fissile mass by a measurement of the number of neutron signals in time intervals. The method uses the stochastic transport equation to express the first three central moments (mean ...

    21 April 2012

  13. Experimental determination of the 41Ca(n,α)38Ar reaction cross section up to 80 keV, and calculation of the Maxwellian averaged cross section at stellar temperatures

    The 41Ca(n,α)38Ar reaction cross section was studied at the linear accelerator GELINA of the Institute for Reference Materials and Measurements in Geel (Belgium) and was determined up to a neutron energy of about 80 keV using the time-of-flight technique. ...

    08 May 2012

  14. Giant Magnetoelastic Interaction in UFe2

    Using the unique coverage of (Q, ω) space available on the BRISP spectrometer, we have investigated the low Q dynamical response of a single crystal of UFe2. A strong inelastic signal was found with a dispersion corresponding to the transverse acoustic ph ...

    07 June 2012

  15. Preparation and characterisation of thin film nuclear targets for neutron physical measurements

    In the target preparation laboratory of the Insitute for Reference Materials and Measurements, lithium fluoride, 10B, gold and tristearin thin films are produced by physical vapour deposition for neutron spectroscopy experiments and for neutron cross sect ...

    04 July 2012

  16. Partition between the fission fragments of the excitation energy and of the neutron multiplicity at scission in low-energy fission

    The partition between the light (L) and the heavy (H) fission fragments of the excitation energy available at scisssion is studied in the frame of the sudden approximation i.e., under the assumption that the neck rupture and the absorption of the neck pie ...

    20 July 2012

  17. Neutron spectra measurement and comparison of the HFR and THOR BNCT beams

    This paper aims to measure the spectra of HB11 (high flux reactor, HFR) and the Tsing Hua open-pool reactor (THOR) boron neutron capture therapy (BNCT) beams by multiple activation foils. The selfshielding corrections were made with the aid of MCNP calcul ...

    03 August 2012

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

    As output of the Point by Point model (taking into account the entire fission fragment range) and of the most probable fragmentation approach (working with one fragmentation and average values of model parameters) not only prompt neutron quantities are pr ...

    24 October 2012

  19. Measurement of the neutron-induced fission cross-section of 243Am relative to 235U from 0.5 to 20 MeV

    The ratio of the neutron-induced fission cross-sections of 243Am and 235U was measured in the energy range from 0.5 to 20 MeV with uncertainties of ≈ 4 %. The experiment was performed at the CERN n_TOF facility using a fast ionization chamber. With the go ...

    24 October 2012

  20. Testing on novel neutron detectors as alternative to 3He for security applications

    Detection of illicit trafficking of nuclear material relies on the detection of the radiation emitted. In the case of plutonium, one of the characteristic signatures derives from neutron emission. For this reason, neutron detectors cover an important role ...

    24 October 2012

  21. Gamma-ray measurements with LaBr3: Ce detectors- thinking outside the box

    Recently developed cerium-doped lanthanum bromide (LaBr3:Ce) scintillation detectors have shown to possess promising properties with respect to the detection of γ-rays compared to previously known materials. In this work however, we demonstrate how these ...

    24 October 2012

  22. Coupled Neutronics Thermal-Hydraulics Analysis using Monte Carlo and Sub-channel Codes

    The accuracy and the degree of spatial resolution of safety studies, required for new reactor concepts, imply the use of coupled 3D neutronic and 3D thermal hydraulic codes. Tools to perform the coupling between neutronic codes both deterministic and stoc ...

    24 October 2012

  23. Quasi-stellar neutrons from the 7Li(p,n)7Be reaction with an energy-broadened proton beam

    Neutrons produced by the 7Li(p,n)7Be reaction close to the reaction threshold are widely used to measure the cross section of s-process nucleosynthesis reactions. While experiments have been performed so far with Van de Graaff accelerators, future use of ...

    24 October 2012

  24. The ideal neutron energy spectrum of 241AmLi(alpha,n)10B sources

    The pure and unperturbed (ideal, at birth) spectra of 241AmLi(alpha,n)10B sources were determined using Monte Carlo simulations, along with the neutron spectrum measured outside a source’s encapsulation. Various parameters that affect photon and neutron y ...

    07 November 2012

  25. A new approach to prompt fission neutron TOF data treatment

    The prompt neutron emission in spontaneous fission of Cf-252 has been investigated applying digital signal electronics along with associated digital signal processing algorithms. A new mathematical approach, applicable to single events, was developed for ...

    14 December 2012