P. Schillebeeckx
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View article: Resolved Resonance Evaluation for Neutron Interactions with <sup>103</sup> Rh up to 8 keV
Resolved Resonance Evaluation for Neutron Interactions with <sup>103</sup> Rh up to 8 keV Open
International audience
View article: Nuclear education and training activities of the Joint Research Centre of the European Commission: Maintaining and enhancing nuclear skills and competences
Nuclear education and training activities of the Joint Research Centre of the European Commission: Maintaining and enhancing nuclear skills and competences Open
Within the Euratom Research and Training Programme, the European Commission's Joint Research Centre (JRC) implements nuclear education and training initiatives which support EU policy priorities and contribute to maintaining and developing…
View article: The nuclear research infrastructures open access scheme of the Joint Research Centre (JRC) at the European Commission – Contributions to education, training, mobility and scientific excellence
The nuclear research infrastructures open access scheme of the Joint Research Centre (JRC) at the European Commission – Contributions to education, training, mobility and scientific excellence Open
Independently of the position of a country relatively to the use or not of nuclear in their energy mix, there will be always a need for competent and well-trained people, going from the development of innovative reactors to decommissioning…
View article: Generation of particle self-shielded neutron cross-sections for the Monte-Carlo code TRIPOLI-4<sup>®</sup>
Generation of particle self-shielded neutron cross-sections for the Monte-Carlo code TRIPOLI-4<sup>®</sup> Open
Self-shielding effects of micrometric particles randomly distributed in nuclear materials were the subject of extensive studies. These effects are known as a double-heterogeneity problem due to “microscopic” heterogeneities, involving the …
View article: Experimental setup of the <sup>239</sup>Pu neutron capture and fission cross-section measurements at n_TOF, CERN
Experimental setup of the <sup>239</sup>Pu neutron capture and fission cross-section measurements at n_TOF, CERN Open
The experimental setup of the new measurement of 239 Pu fission and capture cross-section in the n_TOF time-of-flight facility at CERN is presented. The measurement aims to address the needs and demands of nuclear data users. The experimen…
View article: An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation
An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation Open
A method to determine the neutron production rate of a spent nuclear fuel segment sample by means of non-destructive assay conducted under standard controlled-area conditions is described and demonstrated. A neutron well counter designed f…
View article: Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel
Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel Open
The accuracy of source term predictions is an important factor which determines the efficiency of interim and final storage of spent nuclear fuel. To minimize the required number of storage containers and to minimize the volume and mass of…
View article: ORNL FY22 NCSP Time-of-Flight Measurement [Slides]
ORNL FY22 NCSP Time-of-Flight Measurement [Slides] Open
This presentation covers the ORNL FY22 NCSP Time-of-Flight measurements. Key take-aways from this presentation include that the process was initiated in FY22. The Lease starts Mar. FY23 (delayed). Finally, that there has been a 30% increas…
View article: Experimental work on Nuclear Astrophysics at JRC GELINA facility
Experimental work on Nuclear Astrophysics at JRC GELINA facility Open
JRC Geel operates a neutron time-of-flight facility based on an electron accelerator, GELINA. Experimental setups to determine total and reaction cross sections (capture, elastic and inelastic scattering, fission and charged particle react…
View article: Nuclear data activities at GELINA
Nuclear data activities at GELINA Open
Over the last decade, efforts were made to improve the performance of the experimental set-ups at the Geel Electron Linear Accelerator (GELINA) neutron time-of-flight facility of the European Commission Joint Research Centre (EC-JRC). Thes…
View article: On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
On the estimation of nuclide inventory and decay heat: a review from the EURAD European project Open
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclear Fuel (SNF), as part of the European project EURAD (Work Package 8), is presented. Both measured nuclide concentrations from Post Irradiat…
View article: Zirconium Nuclear Data Campaign: Measurement of <sup>90</sup>Zr (<i>n, γ</i>) cross section
Zirconium Nuclear Data Campaign: Measurement of <sup>90</sup>Zr (<i>n, γ</i>) cross section Open
The isotopes of Zr with A = [90, 91, 92, 94] make up more than 97% of naturally occurring Zr and are important to many nuclear applications such as nuclear reactors. One of the attractive qualities of naturally occurring Zr isotopes is tha…
View article: Neutron cross section measurements for BUC approaches
Neutron cross section measurements for BUC approaches Open
Criticality safety analysis is required at various stages of the back-end of the fuel cycle, i.e. reprocessing, transport, storage and disposal of spent nuclear fuel (SNF). To account for the reduction in reactivity due to fuel burnup, the…
View article: Measurement of the <sup>235</sup>U(n,f) cross section relative to the <sup>10</sup>B(n,α) reaction with Micromegas detectors at the CERN n_TOF facility: First results
Measurement of the <sup>235</sup>U(n,f) cross section relative to the <sup>10</sup>B(n,α) reaction with Micromegas detectors at the CERN n_TOF facility: First results Open
Neutron cross section measurements are often made relative to a neutron cross section standard. Thus, the accuracy of the neutron standards determines the best possible accuracy of the neutron measurements. The 235 U(n,f) cross section is …
View article: Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo Open
SFC is a work package in Eurad that investigates issues related to the properties of the spent nuclear fuel in the back-end of the nuclear fuel cycle. Decay heat, nuclide inventory, and fuel integrity (mechanical and otherwise), and not le…
View article: Time-of-flight measurements of MINERVE samples containing fission products and neutron absorbing isotopes
Time-of-flight measurements of MINERVE samples containing fission products and neutron absorbing isotopes Open
The zero-power reactor MINERVE (CEA Cadarache) was designed to perform reactivity worth measurements by the oscillation technique. The various experimental programs, undertaken for the last thirty years, involved cylindrical samples with a…
View article: Improving Zr cross sections: <sup>90</sup>Zr(n, y) [Slides]
Improving Zr cross sections: <sup>90</sup>Zr(n, y) [Slides] Open
This presentation covers key take-aways such as the first of 4 isotopes (90,91,92,94) to be measured. 91Zr is currently being measured at GELINA. Once all measurements are done a join evaluation with SAMMY will be undertaken. Further, ther…
View article: Zr Nuclear Data Campaign: Measurement of <sup>90</sup>Zr(n,<em>γ</em>) cross section [Slides]
Zr Nuclear Data Campaign: Measurement of <sup>90</sup>Zr(n,<em>γ</em>) cross section [Slides] Open
energies < 0.1 MeV, and uncertainty greater than 20% for energies > 0.1 MeV for the majority of natural Zr isotopes. This motivated the Nuclear Criticality Safety Program (NCSP) to embark on a campaign to accurately measure and evaluate th…
View article: Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat
Blind Benchmark Exercise for Spent Nuclear Fuel Decay Heat Open
The decay heat rate of five spent nuclear fuel assemblies of the pressurized water reactor type were measured by calorimetry at the interim storage for spent nuclear fuel in Sweden. Calculations of the decay heat rate of the five assemblie…
View article: ORNL Neutron Cross Section Measurements of <sup>90</sup>Zr [Slides]
ORNL Neutron Cross Section Measurements of <sup>90</sup>Zr [Slides] Open
which performed ND experiments, data analysis, and evaluations to produce ENDF files for the ND libraries as identified in the NCSP Five-Year Plan. Before being submitted to the ENDF library, files were processed and tested for performance…
View article: EVALUATING PEAK AREA UNCERTAINTIES IN CONNECTION TO PASSIVE GAMMA MEASUREMENTS OF SPENT NUCLEAR FUEL
EVALUATING PEAK AREA UNCERTAINTIES IN CONNECTION TO PASSIVE GAMMA MEASUREMENTS OF SPENT NUCLEAR FUEL Open
In many countries, spent nuclear fuel is planned to be stored in a geological repository. Before the final encapsulation, safety parameters such as decay heat, criticality, and dose rate need to be ensured. A gamma scan of the spent nucl…