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Measurements of inelastic scattering and (n,xn)-cross sections with the (n,xnγ)-technique are per... more Measurements of inelastic scattering and (n,xn)-cross sections with the (n,xnγ)-technique are performed at the GELINA neutron time-of-flight facility with two arrays consisting of high purity germanium detectors, GAINS and GRAPHEME. These measurements provide important nuclear data for criticality, reactivity and power distribution estimates in current and advanced power reactors, for the development of active material interrogation techniques for security and safeguards, and for background studies supporting the search for neutrinoless double-beta decay in experiments like GERDA, and MAJORANA and for weakly interacting massive particles. Despite significant advances in modeling, such cross sections still pose a major challenge to nuclear theory at the level of the required accuracy. GAINS is an array consisting of 12 large volume detectors used to study inelastic scattering from C to Bi with high incident neutron energy resolution. GRAPHEME using four planar detectors, is tailored ...
Much of the world is in cyber space. Cyber security is a huge issue with many facets that involve... more Much of the world is in cyber space. Cyber security is a huge issue with many facets that involve aspects from the security management on a company's or organization's side of the equation to the hackers trying to breach said security to the user's themselves and their private and personal information. Cyber security has brought about research, discussion, papers, tools for monitoring, tools for management, and so on. Much of the focus is on the company's or organization's side of the equation and the protection of their and their client's (the user) information. The most common paradox is weighing the risk to the cost of implementation, but through the company's or organization's point of view. What about the point of view of client of the company or organization? These are the people that use the company's or organization's web site and trust in the company or organization with their personally identifiable information. How much security is ...
ABSTRACT Abstract Over the last decade, the EC–JRC–IRMM, in collaboration with other institutes s... more ABSTRACT Abstract Over the last decade, the EC–JRC–IRMM, in collaboration with other institutes such as INRNE Sofia (BG), INFN Bologna (IT), ORNL (USA), CEA Cadarache (FR) and CEA Saclay (FR), has made an intense effort to improve the quality of neutron-induced cross section data in the resonance region. These improvements relate to both the infrastructure of the facility and the measurement setup, and the data reduction and analysis procedures. As a result total and reaction cross section data in the resonance region with uncertainties better than 0.5 % and 2 %, respectively, can be produced together with evaluated data files for both the resolved and unresolved resonance region. The methodology to produce full ENDF compatible files, including covariances, is illustrated by the production of resolved resonance parameter files for 241Am, Cd and W and an evaluation for 197Au in the unresolved resonance region.
The Geel Electron Linear Accelerator (GELINA) was used to measure neutron total and capture cross... more The Geel Electron Linear Accelerator (GELINA) was used to measure neutron total and capture cross sections of {sup 182,183,184,186}W and {sup 63,65}Cu in the energy range from 100 eV to â200 keV using the time-of-flight method. GELINA is the only high-power white neutron source with excellent timing resolution and ideally suited for these experiments. Concerns about the use of existing cross-section data in nuclear criticality calculations using Monte Carlo codes and benchmarks were a prime motivator for the new cross-section measurements. To support the Nuclear Criticality Safety Program, neutron cross-section measurements were initiated using GELINA at the EC-JRC-IRMM. Concerns about data deficiencies in some existing cross-section evaluations from libraries such as ENDF/B, JEFF, or JENDL for nuclear criticality calculations were the prime motivator for new cross-section measurements. Over the past years many troubles with existing nuclear data have emerged, such as problems relat...
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2009
It has been suggested that the capture and scattering cross sections of natural cadmium are not w... more It has been suggested that the capture and scattering cross sections of natural cadmium are not well described by the resonance parameters that are given in the evaluated data files. In particular, doubts on the parameters of the first resonance of 113Cd at 0.178eV have been raised. This resonance is of high importance in the interpretation in many integral experiments,
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2010
ABSTRACT The influence of target characteristics on results of neutron-induced cross-section meas... more ABSTRACT The influence of target characteristics on results of neutron-induced cross-section measurements is discussed. The basic principles of total and reaction cross-section experiments are described. The discussion shows that each application needs targets with specific requirements, which are characterized for quantities, such as the total number of nuclei per unit area, effective area and homogeneity. The result of such a characterization can have a strong impact on the total uncertainty of the quantities deduced from the measured data. Based on the measurement principles and on practical experience, recommendations for specific cross-section measurements are presented. These recommendations refer to both the target properties and to the methods used for target characterization. In addition, a characterization method based on the use of neutron resonances is presented. This method can be used to determine the presence and quantity of contaminants and impurities which have a strong impact on the results of cross-section measurements.
ABSTRACT Transmission measurements have been performed to determine the total cross section for n... more ABSTRACT Transmission measurements have been performed to determine the total cross section for neutron-induced reactions with 197Au in the energy region from 4keV to 108keV. The experiments were carried out at a 50m measurement station of the time-of-flight facility GELINA using a 6Li glass scintillator. The average total cross section as a function of neutron energy was derived after correcting the observed average transmission for cross section fluctuations due to resonance structures. The results have been compared with literature data and with the total cross section resulting from a dispersive coupled-channel optical model potential. The neutron strength function for s -wave neutrons and an orbital-independent scattering radius, together with their covariance matrix, have been derived in the neutron energy region between 4keV and 108keV through a parameterization of the total cross section based on a nuclear reaction theory.
Measurements of inelastic scattering and (n,xn)-cross sections with the (n,xnγ)-technique are per... more Measurements of inelastic scattering and (n,xn)-cross sections with the (n,xnγ)-technique are performed at the GELINA neutron time-of-flight facility with two arrays consisting of high purity germanium detectors, GAINS and GRAPHEME. These measurements provide important nuclear data for criticality, reactivity and power distribution estimates in current and advanced power reactors, for the development of active material interrogation techniques for security and safeguards, and for background studies supporting the search for neutrinoless double-beta decay in experiments like GERDA, and MAJORANA and for weakly interacting massive particles. Despite significant advances in modeling, such cross sections still pose a major challenge to nuclear theory at the level of the required accuracy. GAINS is an array consisting of 12 large volume detectors used to study inelastic scattering from C to Bi with high incident neutron energy resolution. GRAPHEME using four planar detectors, is tailored ...
Much of the world is in cyber space. Cyber security is a huge issue with many facets that involve... more Much of the world is in cyber space. Cyber security is a huge issue with many facets that involve aspects from the security management on a company's or organization's side of the equation to the hackers trying to breach said security to the user's themselves and their private and personal information. Cyber security has brought about research, discussion, papers, tools for monitoring, tools for management, and so on. Much of the focus is on the company's or organization's side of the equation and the protection of their and their client's (the user) information. The most common paradox is weighing the risk to the cost of implementation, but through the company's or organization's point of view. What about the point of view of client of the company or organization? These are the people that use the company's or organization's web site and trust in the company or organization with their personally identifiable information. How much security is ...
ABSTRACT Abstract Over the last decade, the EC–JRC–IRMM, in collaboration with other institutes s... more ABSTRACT Abstract Over the last decade, the EC–JRC–IRMM, in collaboration with other institutes such as INRNE Sofia (BG), INFN Bologna (IT), ORNL (USA), CEA Cadarache (FR) and CEA Saclay (FR), has made an intense effort to improve the quality of neutron-induced cross section data in the resonance region. These improvements relate to both the infrastructure of the facility and the measurement setup, and the data reduction and analysis procedures. As a result total and reaction cross section data in the resonance region with uncertainties better than 0.5 % and 2 %, respectively, can be produced together with evaluated data files for both the resolved and unresolved resonance region. The methodology to produce full ENDF compatible files, including covariances, is illustrated by the production of resolved resonance parameter files for 241Am, Cd and W and an evaluation for 197Au in the unresolved resonance region.
The Geel Electron Linear Accelerator (GELINA) was used to measure neutron total and capture cross... more The Geel Electron Linear Accelerator (GELINA) was used to measure neutron total and capture cross sections of {sup 182,183,184,186}W and {sup 63,65}Cu in the energy range from 100 eV to â200 keV using the time-of-flight method. GELINA is the only high-power white neutron source with excellent timing resolution and ideally suited for these experiments. Concerns about the use of existing cross-section data in nuclear criticality calculations using Monte Carlo codes and benchmarks were a prime motivator for the new cross-section measurements. To support the Nuclear Criticality Safety Program, neutron cross-section measurements were initiated using GELINA at the EC-JRC-IRMM. Concerns about data deficiencies in some existing cross-section evaluations from libraries such as ENDF/B, JEFF, or JENDL for nuclear criticality calculations were the prime motivator for new cross-section measurements. Over the past years many troubles with existing nuclear data have emerged, such as problems relat...
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2009
It has been suggested that the capture and scattering cross sections of natural cadmium are not w... more It has been suggested that the capture and scattering cross sections of natural cadmium are not well described by the resonance parameters that are given in the evaluated data files. In particular, doubts on the parameters of the first resonance of 113Cd at 0.178eV have been raised. This resonance is of high importance in the interpretation in many integral experiments,
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2010
ABSTRACT The influence of target characteristics on results of neutron-induced cross-section meas... more ABSTRACT The influence of target characteristics on results of neutron-induced cross-section measurements is discussed. The basic principles of total and reaction cross-section experiments are described. The discussion shows that each application needs targets with specific requirements, which are characterized for quantities, such as the total number of nuclei per unit area, effective area and homogeneity. The result of such a characterization can have a strong impact on the total uncertainty of the quantities deduced from the measured data. Based on the measurement principles and on practical experience, recommendations for specific cross-section measurements are presented. These recommendations refer to both the target properties and to the methods used for target characterization. In addition, a characterization method based on the use of neutron resonances is presented. This method can be used to determine the presence and quantity of contaminants and impurities which have a strong impact on the results of cross-section measurements.
ABSTRACT Transmission measurements have been performed to determine the total cross section for n... more ABSTRACT Transmission measurements have been performed to determine the total cross section for neutron-induced reactions with 197Au in the energy region from 4keV to 108keV. The experiments were carried out at a 50m measurement station of the time-of-flight facility GELINA using a 6Li glass scintillator. The average total cross section as a function of neutron energy was derived after correcting the observed average transmission for cross section fluctuations due to resonance structures. The results have been compared with literature data and with the total cross section resulting from a dispersive coupled-channel optical model potential. The neutron strength function for s -wave neutrons and an orbital-independent scattering radius, together with their covariance matrix, have been derived in the neutron energy region between 4keV and 108keV through a parameterization of the total cross section based on a nuclear reaction theory.
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