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Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2021-01, Vol.986, p.164718, Article 164718

2021

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Delayed gamma-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

EPJ Web of Conferences, 2017, Vol.146, p.9018

2017

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Experiments at the GELINA facility for the validation of the self-indication neutron resonance densitometry technique

EPJ Web of Conferences, 2017, Vol.146, p.9020

2017

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Neutron-induced nuclear data for the MYRRHA fast spectrum facility

EPJ Web of Conferences, 2017, Vol.146, p.9007

2017

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複雑な組成・形状の核燃料を計量管理する中性子共鳴濃度分析法の開発: 粒子状溶融燃料中の核物質非破壊測定技術の開発

日本原子力学会誌ATOMOΣ, 2016, Vol.58(9), pp.563-567

2016

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Experimental work on Nuclear Astrophysics at JRC GELINA facility

Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel

Semi-empirical model to determine pre- and post-neutron fission product yields and neutron multiplicity

Time-of-flight measurements of MINERVE samples containing fission products and neutron absorbing isotopes

Zirconium Nuclear Data Campaign: Measurement of 90Zr (n, γ) cross section

On the estimation of nuclide inventory and decay heat: a review from the EURAD European project

Measurement of the direct particle transport through stochastic media using neutron resonance transmission analysis

BOUNDARY CONDITION MODELING EFFECT ON THE SPENT FUEL CHARACTERIZATION AND FINAL DECAY HEAT PREDICTION FROM A PWR ASSEMBLY

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

Neutron transmission measurements at nELBE

Neutron resonance analysis for nuclear safeguards and security applications

Nuclear data research supported by EURATOM: CHANDA, ERINDA and EUFRAT

Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo

Experimental setup of the 239Pu neutron capture and fission cross-section measurements at n_TOF, CERN

Measurement of the 235U(n,f) cross section relative to the 10B(n,α) reaction with Micromegas detectors at the CERN n_TOF facility: First results

Neutron nuclear data measurements for criticality safety

First Results of the 140Ce(n,γ)141Ce Cross-Section Measurement at n_TOF

On the use of the generalized SPRT method in the equivalent hard sphere approximation for nuclear data evaluation

Imaging of cultural heritage objects using neutron resonances

Americium-241 integral radiative capture cross section in over-moderated neutron spectrum from pile oscillator measurements in the Minerve reactor

Peak shape calibration of a Cadmium Zinc Telluride detector and its application for the determination of uranium enrichment

Delayed gamma-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

Experiments at the GELINA facility for the validation of the self-indication neutron resonance densitometry technique

Neutron-induced nuclear data for the MYRRHA fast spectrum facility

複雑な組成・形状の核燃料を計量管理する中性子共鳴濃度分析法の開発: 粒子状溶融燃料中の核物質非破壊測定技術の開発

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