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Rodriguez, D. C.; Abbas, K.*; Bertolotti, D.*; Bonaldi, C.*; Fontana, C.*; 藤本 正己*; Geerts, W.*; 小泉 光生; Macias, M.*; Nonneman, S.*; et al.
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 8 Pages, 2023/05
Under the MEXT subsidy to improve nuclear security related activities, we present the overview of the JAEA-JRC delayed gamma-ray spectroscopic analysis project. We describe past results, recent joint experiments, and the final goals for this project.
Rodriguez, D. C.; 小泉 光生; Rossi, F.; 高橋 時音; Abbas, K.*; Nonneman, S.*; Pedersen, B.*; Oberstedt, S.*; Schillebeeckx, P.*
Proceedings of International Safeguards; Reflecting on the Past and Anticipating the Future, 7 Pages, 2022/10
Under the MEXT subsidy to develop nuclear security, the ISCN is investigating the Delayed Gamma-ray Spectroscopic analysis technique to evaluate mixed nuclear materials. Primarily we are focusing on developing the analysis for any form of mixed nuclear material, but dominantly used nuclear fuel that is challenging due to the long-lived fission products and minor actinides hiding the U and Pu signatures. We describe the analysis we are developing and the associated instrumentation to interrogate the sample. We show that this can be applied to small samples and assemblies, as well as alternative fuel cycle materials.
Rodriguez, D. C.; Abbas, K.*; 小泉 光生; Nonneman, S.*; Oberstedt, S.*; Pedersen, B.*; Rossi, F.; Schillebeeckx, P.*; 高橋 時音
Proceedings of INMM 63rd Annual Meeting (Internet), 9 Pages, 2022/09
Under the MEXT subsidy to develop nuclear security related technology, we present the overview and ISCN analysis development of the Delayed Gamma-ray Spectroscopic Analysis project. We summarize the past analysis and instrumentation results and highlight how this affects the evaluation of fissile nuclides in spent nuclear fuel. We further discuss the direction of the third development phase.
Rodriguez, D. C.; Abbas, K.*; 小泉 光生; Nonneman, S.*; Rossi, F.; 高橋 時音
Nuclear Instruments and Methods in Physics Research A, 1014, p.165685_1 - 165685_10, 2021/10
被引用回数：4 パーセンタイル：38.95(Instruments & Instrumentation)Under the MEXT subsidy on research for improving nuclear security related development, we designed the Delayed Gamma-ray Californium Test (DGCT) instrument. From He-3 count-rate experiments performed in collaboration with the European Commission Joint Research Centre, we show the effective neutron flux entering the sample space. Further, we show delayed gamma-ray spectra of both U and Pu samples as well as a comparison to the background from Cf activation of the environment. Finally, we make comparisons to earlier spectra obtained using PUNITA, including relative fission capability, spectral signature, and mass correlations.
Rodriguez, D. C.; Abbas, K.*; 小泉 光生; Lee, H.-J.; Nonneman, S.*; Pedersen, B.*; Rossi, F.; 高橋 時音
Proceedings of 2021 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC) (Internet), 3 Pages, 2021/10
Under the MEXT subsidy for the promotion of nuclear security related improvement, we will describe our efforts of Delayed Gamma-ray Spectroscopy for application toward spent nuclear fuel in reprocessing plants. This talk in the set of presentations will focus on the latest and new results of the JAEA/ISCN analysis development. In particular it will describe comparisons between the JAEA/ISCN DGS Monte Carlo and other simulation packages with measured spectra collected in collaboration with the EC/JRC.
Cf irradiator for delayed gamma-ray spectroscopy applicationsTohamy, M.*; Abbas, K.*; Nonneman, S.*; Rodriguez, D. C.; Rossi, F.
Applied Radiation and Isotopes, 173, p.109694_1 - 109694_7, 2021/07
被引用回数：5 パーセンタイル：41.70(Chemistry, Inorganic & Nuclear)An experiment to evaluate a neutron flux for an irradiator using Cf was performed by the EC-JRC by applying the Westcott method to indium and gold activation foils. ISCN DG members subsequently developed an MCNP model for a flux comparison within the MEXT subsidiary budget for the promotion of applications related to nuclear security. The flux values are able to show values within 10% for the thermal evaluation with larger differences in the resonance peak energies. Contrarily, there are differences in the reaction rate and peak-count data-model comparisons that could provide new opportunities of basic science research.
Rodriguez, D. C.; Abbas, K.*; Crochemore, J.-M.*; 小泉 光生; Nonneman, S.*; Pedersen, B.*; Rossi, F.; 瀬谷 道夫*; 高橋 時音
EPJ Web of Conferences, 239, p.17005_1 - 17005_5, 2020/09
被引用回数：1 パーセンタイル：62.10(Nuclear Science & Technology)While nondestructive assay techniques would improve the efficiency and time to quantify high-radioactivity nuclear material, there are no passive NDA techniques available to directly verify the U and Pu content. The JAEA and JRC are collaboratively developing the Delayed Gamma-ray Spectroscopy to evaluate the fissile composition from the unique fission product yield distributions. We are developing an Inverse Monte Carlo method that simulates the interrogation and evaluates the individual contributions to the composite spectrum. While the current nuclear data affects the ability to evaluate the composition, the IMC analysis method can be used to determine the systematic uncertainty contributions and has the potential to improve the nuclear data. We will present the current status of the DGS collaborative work as it relates to the development of the DGS IMC analysis.
Rossi, F.; Abbas, K.*; 小泉 光生; Lee, H.-J.; Nonneman, S.*; Pedersen, B.*; Rodriguez, D. C.; 高橋 時音
no journal, ,
In the field of nuclear material samples safeguard verifications, mixed high-radioactivity nuclear material in facility like reprocessing nuclear plant are challenging. Addressing this, the JAEA/ISCN is developing a DG-nondestructive assay technique. We successfully completed several experiments in collaboration with the EC/JRC to evaluate the instrumentation requirements of a compact instrument. In principle, a neutron source is used to produce neutrons that are then thermalized in a moderator before reaching the sample to induce fission. The optimization of the moderator is crucial to reach an efficient and compact instrument. Having a good thermalized neutron flux enhances the delayed gamma-ray signature of the fissile due to their greater thermal fission cross section compared to the fertile. After the irradiation, the gamma-ray peaks above 3 MeV are analyzed to determine the initial composition of the fissile nuclides. The gamma-ray spectrum and subsequent analysis are strongly affected by the source type; the sample; and the interrogation pattern, driven by the analysis. To investigate all these aspects, we performed several experiments using small standard samples of both Uranium and Plutonium with PUNITA to understand basic principles. These were factored into the JAEA DGCT instrument that was tested in PERLA. This work first describes the PUNITA and PERLA experiments and how these were used to validate the various model designs. From these, further modifications to reach our final instrument concept design for a deuterium-deuterium neutron generator source are presented. This work is supported by MEXT under the subsidy for the "promotion for strengthening nuclear security and the like". This work was done under the agreement between JAEA and EURATOM in the field of nuclear material safeguards research and development.
