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Utilizing nuclear data in delayed gamma-ray spectroscopy inverse Monte Carlo analysis

Rodriguez, D.; 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

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.


Utilizing PUNITA experiments to evaluate fundamental delayed gamma-ray spectroscopy interrogation requirements for nuclear safeguards

Rodriguez, D.; 小泉 光生; Rossi, F.; 瀬谷 道夫; 高橋 時音; Bogucarska, T.*; Crochemore, J.-M.*; Pedersen, B.*; 高峰 潤

Journal of Nuclear Science and Technology, 57(8), p.975 - 988, 2020/08

 被引用回数:1 パーセンタイル:24.17(Nuclear Science & Technology)

Present safeguards verification methods of high-radioactivity nuclear material use destructive analysis techniques since passive nondestructive techniques are incapable of determining the nuclear material content. To improve this verification process, the JAEA and EC-JRC Ispra, Italy have been collaborating to develop delayed gamma-ray spectroscopy for composition analysis of the fissile nuclides as an aspect of the MEXT subsidy for improving nuclear security and the like. Multiple experiments were performed over three years using PUNITA to interrogate U and Pu samples to determine the signature from the short-lived fission products. We observed many gamma rays useful to determine the composition of a mixed nuclear material sample. Presented here are the results of these measurements with correlations to the interrogation, mass, volume, and sample homogeneity.


Corrigendum to "Model design of a compact delayed gamma-ray moderator system using $$^{252}$$Cf for safeguards verification measurements" [Appl. Radiat. Isot. 148C (2019) 114-125]

Rodriguez, D.; Rossi, F.; 高橋 時音; 瀬谷 道夫*; 小泉 光生

Applied Radiation and Isotopes, 159, P. 109083_1, 2020/05

 被引用回数:0 パーセンタイル:100(Chemistry, Inorganic & Nuclear)

Under the MEXT subsidy to improve nuclear security related development, there was a mistake made in the MCNP model of our initial Cf moderator design. This corrigendum includes the description of the mistake and the results from correcting this.


Shell evolution of $$N$$ = 40 isotones towards $$^{60}$$Ca; First spectroscopy of $$^{62}$$Ti

Cort$'e$s, M. L.*; Rodriguez, W.*; Doornenbal, P.*; Obertelli, A.*; Holt, J. D.*; Lenzi, S. M.*; Men$'e$ndez, J.*; Nowacki, F.*; 緒方 一介*; Poves, A.*; et al.

Physics Letters B, 800, p.135071_1 - 135071_7, 2020/01

 被引用回数:3 パーセンタイル:13.44(Astronomy & Astrophysics)

ガンマ線分光による$$N$$=40同調体である$$^{62}$$Tiの分光学研究を$$^{63}$$V($$p$$,$$2p$$)$$^{62}$$TiをRIBFで行った。今回初めて測定された$$2_1^+ rightarrow 0_{rm gs}^+$$$$4_1^+ rightarrow 2_1^+$$の遷移はTiの基底状態が変形していることを示唆した。これらのエネルギーは近傍核の$$^{64}$$Crや$$^{66}$$Feと比較して大きく、したがって四重極集団運動が小さくなっていることが示唆される。今回の結果は大規模殻模型計算によって良く再現される一方、第一原理計算や平均場模型では今回の結果は再現されなかった。


Quasifree neutron knockout from $$^{54}$$Ca corroborates arising $$N=34$$ neutron magic number

Chen, S.*; Lee, J.*; Doornenbal, P.*; Obertelli, A.*; Barbieri, C.*; 茶園 亮樹*; Navr$'a$til, P.*; 緒方 一介*; 大塚 孝治*; Raimondi, F.*; et al.

Physical Review Letters, 123(14), p.142501_1 - 142501_7, 2019/10

 被引用回数:8 パーセンタイル:16.18(Physics, Multidisciplinary)

$$^{54}$$Caでは中性子魔法数34が現れると考えられているが、その直接的な実験的証拠を得るため、$$^{54}$$Caからの中性子ノックアウト反応$$^{54}$$Ca($$p,pn$$)$$^{53}$$Caによって生成される状態を理化学研究所のRI Beam Factoryによって調べた。基底状態および2.2MeVの励起状態が強く生成され、1.7MeVの励起状態の生成量は小さかった。$$^{53}$$Caの運動量分布から、基底状態および2.2MeVの励起状態は$$p$$軌道の中性子を叩き出して得られた状態であることが明らかになった。DWIA計算によって得られた分光学的因子から、$$^{54}$$Caは$$p$$軌道がほぼ完全に占有された閉殻構造を持つことが明らかになり、中性子魔法数34の出現が確実なものとなった。


Effective capacity-building development based on good practices from the additional protocol implementation

Rodriguez, P.; 千崎 雅生; 関根 恵

Proceedings of INMM 60th Annual Meeting (Internet), 9 Pages, 2019/07



Delayed gamma-ray spectroscopy for nuclear material analysis, 2; Design of a practical system with DD neutron generator

Rossi, F.; Rodriguez, D.; 高橋 時音; 瀬谷 道夫; 小泉 光生

Proceedings of INMM 60th Annual Meeting (Internet), 7 Pages, 2019/07

To safeguard nuclear material at facilities like reprocessing plants, new active-interrogation nondestructive assay techniques are needed. We are developing a new delayed gamma-ray spectroscopy (DGS) system to be used together with current verification methods, like hybrid k edge/X ray densitometry, to quantify the fissile composition in high-radioactivity nuclear material samples. DGs quantifies the composition by comparing the ratios of gamma-ray peaks with energy above 3 MeV from short-lived fission products produced during irradiation of the sample by a high-rate external neutron source. Utilizing thermal neutrons allows more fission events to be produced by fissile nuclides (U-235, Pu-239 and Pu-241) to overcome the shielding required to reduce the low energy passive background from the long-lived fission products. While the dominant external sources proposed for this application are DT neutron generators, we are designing a compact system with the use of a DD neutron generator that produces neutrons with starting energies that are easier to moderate and retain. The main differences between the two systems will be presented here along with the description of the current design of our system. This technological research and development was supported by the Japanese government (MEXT). This work was performed under the MEXT subsidy to strengthen nuclear security related activities.


Model design of a compact delayed gamma-ray moderator system using $$^{252}$$Cf for safeguards verification measurements

Rodriguez, D.; Rossi, F.; 高橋 時音; 瀬谷 道夫; 小泉 光生

Applied Radiation and Isotopes, 148, p.114 - 125, 2019/06

 被引用回数:3 パーセンタイル:20.8(Chemistry, Inorganic & Nuclear)

Delayed gamma-ray spectroscopy is an active-NDA technique used to determine the composition of HRNM samples by peak-ratio comparison of GRs above 3-MeV from the short-lived fission products. Filtering out the passive GRs from long-lived FPs reduces the DGS signal, so thermal neutrons are used to induce more fission events from fissile nuclides. We are developing a compact system to moderate $$sim$$ 2-MeV neutrons that are easier to moderate than 14-MeV neutrons from DT generators. This work describes the ideal moderator optimization for a $$^{252}$$Cf source that results in $$25.9times10^{-4}$$ cm$$^{-2}$$ $$n_{source}^{-1}$$ passing through the sample space with $$geq$$ 70% of those below 1-eV. Practical modifications resulted in $$leq$$ 20% reductions compared to the optimized design. Evaluations of DGS signals and backgrounds conclude that only a 21-MBq $$^{252}$$Cf source is required.


Delayed gamma-ray spectroscopy, 2; Design study of moderator for a practical system

Rossi, F.; Rodriguez, D.; 高橋 時音; 瀬谷 道夫; 小泉 光生

日本核物質管理学会第39回年次大会論文集(CD-ROM), 3 Pages, 2018/11



Delayed gamma-ray spectroscopy, 1; Phase-I summary, Phase-II preview, and continuous solution monitoring

Rodriguez, D.; Rossi, F.; 高橋 時音; 瀬谷 道夫; 小泉 光生

日本核物質管理学会第39回年次大会論文集(インターネット), 2 Pages, 2018/11

高放射性核物質溶液サンプルの保障措置検認は、Pu/U元素量についてはHKED法で分析され、同位体組成については時間のかかる破壊分析により行われている。同位体組成検認の時間を短くするため、我々は、遅発ガンマ線分光法の開発を、欧州委員会・共同研究センターと共同して行っている。この遅発ガンマ線分光法では、強い$$gamma$$線バックグランドを凌駕するため、核分裂生成核種の発生させる3MeVより高いエネルギーの$$gamma$$線を利用する。我々は、遅発ガンマ線分光のPhase Iの開発概要及びPhase IIの開発計画を発表する。さらに、東海再処理工場(TRP)にて実証した$$gamma$$線(GR)パイプモニタリングについて報告するとともに、$$gamma$$線パイプモニタリング及び自己照射遅発ガンマ線分光技術を含む、再処理施設のプロセスモニタリングについて報告する。


APSN surveys for the coordination of training efforts in Asia; Results and challenges

宮地 紀子; Vidaurre, J.; 堀 雅人; Rodriguez, P.; Robertson, K.*

Proceeding IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 5 Pages, 2018/11

This paper describes ISCN's activities to perform training needs and training providers' surveys, with the objective of facilitating needs analysis; identifying potential gaps in the provision of training; and assisting training providers to optimize their use of existing training capabilities to meet those needs. The baseline training needs and training providers' surveys conducted by the US DOE/NNSA International Nuclear Safeguards and Engagement Program (INSEP) in 2011 are described and then the follow-up surveys of 2015, performed by ISCN, and their results are succinctly explained. A new survey was conducted in 2017 (and expanded in 2018) aimed at countries with Small Quantities Protocols in their safeguards agreements. The results of these surveys and the follow-up actions mandated by the Asia Pacific Safeguards Network (APSN) are also included in this paper.


Concepts for and demonstration of gamma-ray process monitoring for reprocessing facilities

Rodriguez, D.; 谷川 聖史; 瀬谷 道夫; 中村 仁宣

Proceeding IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 6 Pages, 2018/11

To improve safeguards verification capabilities and to reduce the amount of time for IAEA inspectors, the JAEA is developing improved plutonium monitoring capabilities. One of these is a multi-scope concept to continuously monitor purified NM solutions by measuring the NM gamma rays both at the solution tanks and along the transfer pipes. A demonstration of a GR pipe monitoring was performed at the JAEA PCDF and confirmed that this determines both process operations and Pu isotopic composition. This spectrum can be compared to similar spectra collected at tanks to improve CoK. We also propose measuring the delayed GRs from short-lived fission products generated by neutron self-interrogation of the solution in the tanks. The paper will describe an overview of the JAEA gamma-ray process-monitoring concept and the delayed gamma-ray development efforts and technologies to expand safeguards capabilities at reprocessing facilities.


Delayed gamma-ray spectroscopy inverse Monte Carlo analysis method for nuclear safeguards nondestructive assay applications

Rodriguez, D.; Rossi, F.; 瀬谷 道夫; 小泉 光生

Proceedings of 2017 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2017) (Internet), 3 Pages, 2018/11

The JAEA and EC JRC are collaborating to improve the ability to quantify the uranium and plutonium content of highly radioactive and mixed nuclear material for nuclear safeguards verification. A separate program focuses on improving the capability to measure, analyze, and predict the delayed gamma-ray spectrum used to determine the nuclide ratios within a sample. Measurements performed at the JRC-Ispra are used to correlate the observed DGs to the composition that are then used to calibrate a DG Monte Carlo. The MC has the ability to predict expected DGs, provide a sensitivity analysis to optimize future measurements, and can be used to analyze a spectrum using an inverse MC technique. Analyzing MC with this IMC analysis provides a way to determine systematic uncertainty as well as statistical uncertainty when multiple measurements are not feasible. This work will describe the efforts to develop the DGSMC and how it will be utilized for current and future applications.


Demonstration of $$gamma$$-ray pipe-monitoring capabilities for real-time process monitoring safeguards applications in reprocessing facilities

Rodriguez, D.; 谷川 聖史; 西村 和明; 向 泰宣; 中村 仁宣; 栗田 勉; 高峰 潤; 鈴木 敏*; 関根 恵; Rossi, F.; et al.

Journal of Nuclear Science and Technology, 55(7), p.792 - 804, 2018/07

 被引用回数:0 パーセンタイル:100(Nuclear Science & Technology)



Development of delayed gamma-ray spectroscopy for nuclear material analysis

Rodriguez, D.; Rossi, F.; 高橋 時音; 瀬谷 道夫; 小泉 光生; Crochemore, J. M.*; Varasano, G.*; Bogucarska, T.*; Abbas, K.*; Pedersen, B.*

Proceedings of INMM 59th Annual Meeting (Internet), 7 Pages, 2018/07

DGS has great potential for HRNM, since it determines fissile nuclide compositions by correlating the observed DG spectrum to the unique FY of the individual nuclides. Experiments were performed with LRNM using both PUNITA and a JAEA designed Cf-shuffler tested in PERLA. The data was analyzed using an inverse MC method that both determines DG peak intensity correlations and provides an evaluation of the uncertainty of the measurements. The results were used to verify DG signatures for varying fissile compositions, total fissile content, and DGS interrogation timing patterns. Future development will focus on measuring HRNM and designing a compact system by evaluating different neutron sources, moderating materials, and detection capabilities. This presentation summarizes the JAEA/JRC DGS program to date and the future direction of this collaborative work performed using the MEXT subsidy for the promotion of strengthening nuclear security.


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

小泉 光生; Rossi, F.; Rodriguez, D.; 高峰 潤; 瀬谷 道夫; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences, 146, p.09018_1 - 09018_4, 2017/09

 被引用回数:2 パーセンタイル:10.14

Along with the global increase of applications using nuclear materials (NM), the requirements to nuclear security and safeguards for the development of effective characterization methods are growing. Mass verification of NM of low radioactivity is performed using passive non-destructive analysis (NDA) techniques whereas destructive analysis (DA) techniques are applied for accurate analysis of nuclide composition. In addition to the characterization by passive NDA, a sample can be further characterized by active NDA techniques. An active neutron NDA system equipped with a pulsed neutron generator is currently under development for studies of NDA methods. Among the methods DGS uses the detection of decay $$gamma$$-rays from fission products (FP) to determine ratios of fissile nuclides present in the sample. A proper evaluation of such $$gamma$$-ray spectra requires integration of nuclear data such as fission cross-sections, fission yields, half-lives, decay chain patterns, and decay $$gamma$$-ray emission probabilities. The development of the DGS technique includes experimental verification of some nuclear data of fissile materials, as well as development of the device. This presentation will be a brief introduction of the active neutron NDA project and an explanation of the DGS development program.


Delayed gamma-ray spectroscopy, 1; Development and current status

Rodriguez, D.; Rossi, F.; 高峰 潤; 小泉 光生; 瀬谷 道夫; Crochemore, J. M.*; Varasano, G.*; Bogucarska, T.*; Abbas, K.*; Pedersen, B.*

Proceedings of INMM 58th Annual Meeting (Internet), 6 Pages, 2017/07



Delayed gamma-ray spectroscopy, 2; Experimental studies for determination of fissile materials ratios

Rossi, F.; 小泉 光生; Rodriguez, D.; 高峰 潤; 瀬谷 道夫; Pedersen, B.*; Crochemore, J. M.*; Abbas, K.*; Bogucarska, T.*; Varasano, G.*

Proceedings of INMM 58th Annual Meeting (Internet), 7 Pages, 2017/07

保障措置分野では、高線量核物質の核分裂性核種の組成比の独立検認のために、新たな、改良アクティブ問い掛け法NDA技術が必要とされている。原子力機構とJoint Research Centre (JRC)は、サンプルの核分裂生成核種の崩壊からの遅発$$gamma$$線を測定することで、サンプル中核物質の核分裂性核種比を決める遅発$$gamma$$線分光法を共同で開発している。現在、低線量核物質サンプルを用いた測定がいくつかの施設で行われることとなっている。ここで、長半減期核分裂生成核種からの影響を最小限にするために、低エネルギー$$gamma$$線の遮へいと、3MeVを超える高いエネルギーの$$gamma$$線に注目する必要がある。この測定法では、異なる小型中性子源が使用されるが、いずれにおいても中性子エネルギーを熱エネルギー領域まで減速することが必要である。我々は、減速体及び反射体をMCNPを用いて最適化を進めており、また、問い掛け、移動、測定のシークエンスの最適化も進めている。現在進めている測定では、認証されたU/Puサンプルを使用しており、観測する遅発$$gamma$$線を同位体組成に比例する関連付けが可能となる。この発表では、最適化の状況とともに、U/Puサンプル中の核分裂性核種比決定のための実験キャンペーンを紹介する。


$$gamma$$-ray pipe monitoring for comprehensive safeguards process monitoring of reprocessing facilities

Rodriguez, D.; 谷川 聖史; 向 泰宣; 磯前 日出海; 中村 仁宣; Rossi, F.; 小泉 光生; 瀬谷 道夫

Proceedings of INMM 58th Annual Meeting (Internet), 9 Pages, 2017/07



Shape evolution in neutron-rich krypton isotopes beyond N=60; First spectroscopy of $$^{98,100}$$Kr

Flavigny, F.*; Doornenbal, P.*; Obertelli, A.*; Delaroche, J.-P.*; Girod, M.*; Libert, J.*; Rodriguez, T. R.*; Authelet, G.*; 馬場 秀忠*; Calvet, D.*; et al.

Physical Review Letters, 118(24), p.242501_1 - 242501_6, 2017/06

 被引用回数:21 パーセンタイル:11.07(Physics, Multidisciplinary)

The first $$gamma$$-ray spectroscopy of very neutron rich $$^{98,100}$$Kr isotopes was carried out at the RIBF at RIKEN Nishina center. Excited states in these isotopes were populated via (p,2p) reactions using radioactive $$^{99,101}$$Rb beams accelerated to 220 MeV/nucleon. The new data show a significant increase in deformation beyond N=60, as well as competing configurations (shape-coexistence) at low energy. The data were compared with beyond-mean-field calculations which predict level energies in good agreement with observation, and suggest oblate-prolate shape coexistence.

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