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Rodriguez, D.; 赤松 駿介*; Rossi, F.; 鈴木 敏*; 高橋 時音
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 9 Pages, 2024/07
Under the MEXT subsidy to promote nuclear security related activities, we will present the preliminary results from the new Fission Signature Assay Instrument that was fabricated and fully installed in November 2023. We will describe the instrument within the context of the JAEA-JRC collaboration development and the experimental activities planned with it in the larger context of finishing off Phase-III development.
Cantarel, V.; Chupin, F.; Ortega-Charlot, M.*; 山岸 功; 上野 文義
Journal of Nuclear Materials, 592, p.154969_1 - 154969_9, 2024/04
被引用回数：0 パーセンタイル：0.00(Materials Science, Multidisciplinary)When nuclear waste is immobilized in cement or geopolymer, gases may be generated by corrosion and radiolysis. This production must be accurately predicted, and waste loading and countermeasures selected accordingly to avoid overpressure and limit the risk of explosion in the case of dihydrogen (H
). We measured and simulated H generation and release from water-saturated geopolymer confined in a glass bottle under 
Co gamma irradiation. It was observed that confinement of H in the pores of a high pH geopolymer could lead to recombination of more than 99.9% of the hydrogen generated by radiolysis. Shrinkage can allow hydrogen to diffuse between the geopolymer and the vessel, reducing the fraction of recombined H to 90% at our experimental scale. We then used a model to scale up the results of our experiments. The hydrogen release of a saturated geopolymer in a standard 200 L drum is expected to be equivalent to that of a hydraulic binder containing approximately 2% moisture. Harnessing the effects of recombination would make it possible to preserve the capacity of countermeasures such as H absorbers, increase the loading capacity of waste packages, and reduce the cost of nuclear waste immobilization.
Rodriguez, D.; Rossi, F.; 高橋 時音
IEEE Transactions on Nuclear Science, 71(3), p.255 - 268, 2024/03
被引用回数：0 パーセンタイル：0.00(Engineering, Electrical & Electronic)Under the MEXT subsidy to improve nuclear security related capabilities, we are developing the delayed gamma-ray spectroscopic analysis technique. One goal is to develop an inverse Monte Carlo analysis method using spectra from simulations of the interrogation instrument for comparison to the actual measured spectra. This work presents the validity of the Monte Carlo foundation of the analysis compared to experimental results and other simulation codes.
佐藤 優樹
Applied Radiation and Isotopes, 203, p.111083_1 - 111083_9, 2024/01
被引用回数：3 パーセンタイル：46.61(Chemistry, Inorganic & Nuclear)At the Fukushima Daiichi Nuclear Power Station (FDNPS), radioactive substances released during the accident were deposited on various equipment and building structures. During the decommissioning work, an investigation of the deposition of radioactive substances inside the contaminated equipment and structures can provide information on the cause and progression of the accident. This study introduces a quantitative evaluation method of radioactivity using a Compton camera, a type of gamma-ray imager, to investigate the deposition and contamination level of radioactive substances on contaminated objects at the FDNPS. Multiple 
Cs radiation sources with varying radioactivity were placed horizontally in one dimension within the field of view of the Compton camera, and a proof-of-principle study was conducted to evaluate the radioactivity of each source quantitatively.
Rodriguez, D.; 赤松 駿介*; Rossi, F.; 鈴木 敏*; 高橋 時音
第44回日本核物質管理学会年次大会会議論文集(インターネット), 4 Pages, 2023/11
Under the MEXT subsidy for improving nuclear material security related activities, we present the latest JAEA/ISCN delayed gamma-ray instrument, FSAI; preliminary characterization results; and the experimental and analysis development activities planned using it.
Rodriguez, D.; 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.; Rossi, F.
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 9 Pages, 2023/05
Under the MEXT subsidy for the improvement of nuclear security related activities, we will present on the current and future progress of the delayed gamma-ray spectroscopic analysis development. We highlight a paper soon to be released and the plan for finalizing the project goal.
Rossi, F.; 小泉 光生; Rodriguez, D.; 高橋 時音
Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 5 Pages, 2023/05
Since 2015, the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency has been working on the development of the Delayed Gamma-ray Spectroscopy non-destructive assay technique for the quantification of fissile-nuclide content in mixed nuclear materials. Thanks to the efforts and lessons learned from past experiments, the ISCN has successfully designed and fabricated a final integrated instrument. The instrument is composed of a moderator and dose shield where different neutron sources, like Cf-252 and neutron generators, can be inserted to irradiate the sample. Within the moderator, a series of neutron detectors are installed for perform prompt neutron analysis and continuous monitoring of the neutron source emission. Thanks to an innovative transfer system, the sample is then moved to the gamma-ray detector in less than 1.5s providing a fast and reliable movement while being safe from possible contamination. In this work, we will describe the design details of this new instrument. This work is supported by the Japanese Ministry of Education, Culture, Sports, Science, and Technology (MEXT) under the subsidy for the "promotion for strengthening nuclear security and the like".
Rodriguez, D.; 小泉 光生; Rossi, F.; 高橋 時音
Proceedings of 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference (2022 IEEE NSS MIC RTSD) (Internet), 3 Pages, 2022/12
Under the MEXT subsidy to improve nuclear security related activity, we present our latest analytical development of delayed gamma spectroscopic (DGS) analysis for nuclear safeguards. We show the latest results from the ISCN DGS Monte Carlo and comparisons with measured spectra. We highlight differences with other simulation codes, which highlights discrepancies in fission yields from nuclear data and our future direction to improve this for optimal safeguards measurements and reduced uncertainty. We will also summarize how the analysis will be applied with a new instrument designed for small samples for validation of the DGS technique, as well as how this can be applied to full assemblies and alternative fuel cycles.
Rodriguez, D.; 小泉 光生; Rossi, F.; 高橋 時音
第43回日本核物質管理学会年次大会会議論文集(インターネット), 4 Pages, 2022/11
Under the MEXT subsidy to promote the development of nuclear security related activities, we present our latest delayed gamma-ray spectroscopy analysis and instrument developments. We will highlight important past results, current activities, and future plans.
Rossi, F.; 小泉 光生; Rodriguez, D.; 高橋 時音
Proceedings of 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference (2022 IEEE NSS MIC RTSD) (Internet), 2 Pages, 2022/11
To address challenges in the safeguard field for the verification of mixed nuclear materials, the Japan Atomic Energy Agency is developing the Delayed Gamma-ray Spectroscopy non-destructive assay technique. Minimally, this technique requires an external source to induce fission in the sample and a gamma-ray detector to collect the high-energy gamma rays emitted from the decay of fission products. In the development of this technique, deuterium-deuterium neutron generators will replace 
Cf as the external neutron source. The emitted neutrons are then slowed down in the thermal energy range to enhance the delayed gamma-ray signature coming from the fissile nuclides in the sample. The fission product delayed gamma rays with energy above 3 MeV are then collected with a detector located away from the irradiation position to avoid neutron damage. The collected spectrum is then analyzed, and the peak ratios are used to verify the initial composition of the fissile nuclides. Further, source monitors are required to normalize for the source emission to estimate the fissile mass of the sample. In this work, we will first describe our latest development in designing a delayed gamma-ray spectrometer for small mixed nuclear material samples. We will present latest results obtained from activation experiment and neutron detector characterization. Finally, we will present the usage of a new transfer system designed, fabricated, and tested at the Japan Atomic Energy Agency laboratories. 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.
Rodriguez, D.; 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.; 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.
Rossi, F.; 小泉 光生; Rodriguez, D.; 高橋 時音
Proceedings of INMM 63rd Annual Meeting (Internet), 5 Pages, 2022/07
With the initial goal of fissile-nuclide content quantification in small samples containing uranium and plutonium, the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security of the Japan Atomic Energy Agency is developing the Delayed Gamma-ray Spectroscopy non-destructive assay technique. For this, while in the past years several experiments were conducted to prove the feasibility of the technique, a new instrument was designed considering the previous lessons learned. It includes a modular insertion for different neutron sources, like radioisotopes or neutron generators; a gamma-ray detector with improved data acquisition system allowing for real-time dead-time correction; and a full new mechanism for the sample transfer between irradiation and measurement. Together with this, neutron detectors are integrated to supplement the DGS mass analysis and monitor the source intensity. In this work, we will describe the new instrument and the preliminary results obtained from instrument characterization compared to previous experiments. This work is supported by the Japanese Ministry of Education, Culture, Sports, Science, and Technology (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.
and Eu
ions onto sedimentary rock in the presence of gamma-irradiated humic acidZhao, Q.*; 齊藤 毅*; 宮川 和也; 笹本 広; 小林 大志*; 佐々木 隆之*
Journal of Hazardous Materials, 428, p.128211_1 - 128211_10, 2022/04
被引用回数：7 パーセンタイル：47.21(Engineering, Environmental)令和2年度以降の幌延深地層研究計画において原子力機構が取り組んでいる課題の1つである「実際の地質環境における人工バリアの適用性確認」では、坑道周辺の掘削損傷領域において物質移行に関するデータの取得が必要である。本研究では、地下水中に含まれる腐植物質であるフミン酸に着目し、放射線によるフミン酸の分解反応がCsイオンとEuイオンの収着能へ与える影響について、幌延地域の堆積岩を例として調べた。放射線を照射していないフミン酸の存在下では、Euはフミン酸と錯体を形成することで、岩石への収着能は低下する。一方で、放射線の照射によりフミン酸が分解されると、岩石へ収着するEuイオンが増加することが確認された。また、Csの岩石への収着能はフミン酸の影響を受けることが無く、また、放射線により分解されたフミン酸の影響も見られないことが分かった。以上のことから、廃棄体の近傍ではフミン酸の放射線分解により、岩石への収着するEuイオンの割合が大きくなることが考えられる。
線による腐食影響加藤 千明; 山岸 功; 佐藤 智徳; 山本 正弘*
材料と環境, 70(12), p.441 - 447, 2021/12
ゼオライト粒子は福島第一原子力発電所(1F)の汚染水の浄化のためのセシウム吸着塔内で用いられている。使用後のセシウム吸着塔は敷地内で保管されているが、ステンレス鋼製胴部の局部腐食が懸念された。この腐食リスクに対し、線による影響データを照射下電気化学試験装置で取得した。また、内溶液の変化状態を実規模サイズのモックアップ試験装置で検討した。それらの結果から、過酸化水素による電位の上昇がゼオライト粒子の存在で防ぐことができ、塩化物イオンの濃化もそれほど生じないことを明らかにし、局部腐食が相当に小さく抑えられることを示した。
Rodriguez, D.; 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：44.13(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.
-ray spectrometer and its performance under intense Cs and Co radiation fields冠城 雅晃; 島添 健次*; 加藤 昌弘*; 黒澤 忠弘*; 鎌田 圭*; Kim, K. J.*; 吉野 将生*; 庄司 育宏*; 吉川 彰*; 高橋 浩之*
Nuclear Instruments and Methods in Physics Research A, 1010, p.165544_1 - 165544_9, 2021/09
被引用回数：0 パーセンタイル：0.00(Instruments & Instrumentation)2011年の東京電力ホールディングス福島第一原子力発電所の事故以来、世界各地で廃止措置措置に入る原子力施設が増加している。これらの原子力施設では、放射性物質の適切な管理が要求されている。そこで、ガンマ線スペクトル測定技術は、放射性物質の重要な情報を得ることができるため、有益なツールである。さらに、放射性物質の空間情報も重要であるため、ガンマ線イメージングについて求められている。しかしながら、これらの施設には、強度放射線場が広がるため、ガンマ線スペクトル測定やガンマ線イメージングが困難になる。そのため、寸法が5mm 
5mm 5mmの小さなCeBr
シンチレーター4個で分割した線スペクトロメーターを開発した。上記の4個のシンチレーターは、強度放射場に特化したマルチアノード光電子増倍管と組合わせた。私たちは、CsとCoの放射線場で照射試験を実施した。Cs照射場の線量率1375mSv/hにおいて、相対エネルギー分解能が、それぞれのチャンネルで、9.2
0.05%, 8.00.08%, 8.00.03%, 9.0 0.04%であった。
Rossi, F.; Abbas, K.*; 小泉 光生; Lee, H.-J.; Rodriguez, D.; 高橋 時音
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 7 Pages, 2021/08
The Japan Atomic Energy Agency is developing the Delayed Gamma-ray Spectroscopy (DGS) non-destructive assay technique to quantify the fissile-nuclide content in small samples of mixed nuclear materials. One of our primary goals is to develop a compact and efficient DGS instrument to be easily installable into analytical laboratories. The instrument should include an external neutron source and a gamma-ray detection system along with other supporting systems like sample transfer and neutron monitoring. One of the challenges is to design a compact and efficient moderator for commercial neutron sources (e.g. neutron generators or sealed radioactive sources) that emit neutrons with high energy. However, to be able to enhance the gamma-ray signal from fissile materials, thermal neutrons are best due to their higher fission cross-sections. The choice of viable neutron source (neutron spectrum and strength) depends on several considerations (e.g. sample type and interrogation pattern), but also affect the gamma-ray measurement and the consequence analysis. In this work, we will first describe the evaluation results of our Delayed Gamma-ray Test Spectrometer using a Cf source (DGTS-C) from the first experiment carried out in PERLA in collaboration with the European Commission, Joint Research Centre. In association, we will describe how it provided guidance for our demonstration irradiator. Further, we will present our final moderator design concept for a deuterium-deuterium (D-D) neutron generator and present the latest results of data-model comparisons, including those with our PUNITA results. This work is supported by the Japanese Ministry of Education, Culture, Sports, Science, and Technology (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.
Rodriguez, D.; Bogucarska, T.*; 小泉 光生; Lee, H.-J.; Pedersen, B.*; Rossi, F.; 高橋 時音; Varasano, G.*
Nuclear Instruments and Methods in Physics Research A, 997, p.165146_1 - 165146_13, 2021/05
被引用回数：2 パーセンタイル：25.50(Instruments & Instrumentation)Under the MEXT subsidy to strengthen nuclear security related research, the ISCN is developing delayed gamma-ray spectroscopy (DGS) for nuclear safeguards. Here we present results from experiments using the PUNITA instrument in collaboration with JRC-Ispra to evaluate the gamma-ray spectral dependence on interrogation time patterns and number of cycles. Specifically, we investigated the observable gamma rays useful to quantify the 
Pu and 
U contributions. Of the time patterns tested in this study, we determined that irradiating the sample for 60-
followed by a gamma-ray measurement of 60- was the best for a comparable one-hour total interrogation time.
