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瀬川 麻里子; 藤 暢輔; 前田 亮; 甲斐 哲也
Journal of Nuclear Science and Technology, 62(3), p.268 - 277, 2025/03
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)Degerming temperatures with small uncertainties is important for neutron thermometry, required for both fundamental science and industrial applications. Conventionally, neutrons transmitted through a sample in shielded materials are detected. The sample temperature is then derived by analyzing the energy dependence of the transmission neutrons at resonances influenced by the Doppler-broadening effect. However, reducing the temperature-determination uncertainty is extremely hard with the conventional method, because it is determined only by the small changes at the resonances, i.e. temperature-sensitive components, compared to the primary neutrons. Therefore, we propose a new thermometry method named neutron self-indication thermometry (NSIT), which combines the Doppler-broadening effect with a self-indication technique that irradiates the sample and an indicator containing the same nuclide as the sample. The NSIT can enhance temperature sensitivity by measuring prompt gamma-rays to indirectly obtain the temperature-sensitive components at resonances by employing the same resonance twice. This study compared the temperature sensitivity and uncertainty of the conventional and NSIT methods by varying the sample temperatures from 23.0
C to 492.6C. The results demonstrated that the NSIT was approximately 1.6 times more sensitive and had lower uncertainty in determining temperature. These findings highlight the potential of the NSIT as an effective alternative to remote thermometry.
田辺 鴻典*; 米田 政夫; 藤 暢輔; 北村 康則*; 三澤 毅*
日本原子力学会誌ATOMO
, 67(3), p.198 - 202, 2025/03
鉛等で隠匿された
Uに対する非破壊測定技術の開発は、長年、核セキュリティ上の最重要課題と言われてきたが、依然として現場レベルでの検知は困難な状況にある。我々は
Cf回転照射法と呼ばれる新たな核物質非破壊測定手法を提案し、回転照射装置と水チェレンコフ中性子検出器で構成される運搬性の高い現場検知システムを開発、本システムによる核物質検知を実証した。本報では、開発したシステムを概説するとともに今後の展望について解説する。
Cf rotation method with a water Cherenkov neutron detector田辺 鴻典*; 米田 政夫; 藤 暢輔; 北村 康則*; 三澤 毅*; 土屋 兼一*; 相楽 洋*
Scientific Reports (Internet), 14, p.18828_1 - 18828_10, 2024/08
被引用回数：0 パーセンタイル：0.00(Multidisciplinary Sciences)The global challenge of on-site detection of highly enriched uranium (HEU), a substance with considerable potential for unauthorized use in nuclear security, is a critical concern. Traditional passive nondestructive assay (NDA) techniques, such as gamma-ray spectroscopy with high-purity germanium detectors, face significant challenges in detecting HEU when it is shielded by heavy metals. Addressing this critical security need, we introduce an on-site detection method for lead-shielded HEU employing a transportable NDA system that utilizes the Cf rotation method with a water Cherenkov neutron detector. This cost-effective NDA system is capable of detecting 4.17 g of U within a 12 min measurement period using a Cf source of 3.7 MBq. Integrating this system into border control measures can enhance the prevention of HEU proliferation significantly and offer robust deterrence against nuclear terrorism.
I and 
I using the NaI(Tl) spectrometer of the ANNRI beamline at J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 藤 暢輔; 瀬川 麻里子; 前田 亮; 片渕 竜也*
European Physical Journal A, 60(5), p.120_1 - 120_14, 2024/05
被引用回数：0 パーセンタイル：0.00(Physics, Nuclear)The neutron capture cross section of I and I were measured from the thermal to the keV energy region with the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument beamline in the Materials and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex. The neutron capture yield was determined by means of the total energy detection principle with the pulse-height weighting technique. The present cross section results for I were normalized using the saturated resonance method with a thick-enough 
Au and provide good agreement with JENDL-5 from thermal to about 500 keV. A resonance analysis with the REFIT code was performed and the resonance parameters for I below 310 eV are presented in this work. In the case of I, the three largest resonances of I were employed for the cross section normalization. The present results for I are the first experimental data for the neutron region between thermal and 20 eV. The present data display a different energy dependence than that in the JENDL-5 and JEFF-3.3 and much similar to that in ENDF/B-VIII.0. Notwithstanding, good agreement was found at the thermal region between the present measurement of 31.6 
1.3 b and both evaluated and most experimental data.
Ta遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 藤 暢輔; 瀬川 麻里子; 前田 亮
Nuclear Science and Engineering, 198(4), p.786 - 803, 2024/04
被引用回数：1 パーセンタイル：25.62(Nuclear Science & Technology)The neutron transmission ratio and capture yield for Ta were measured in J-PARC MLF ANNRI to improve the accuracy of resonance parameters. The total cross section was determined from the transmission ratio in the energy range from 0.2 to 150 eV. The capture cross section was obtained from the capture yield using the pulse height weighting technique (PHWT) in the energy range from thermal to 150 eV. The obtained transmission ratio and capture cross-section were fitted by the resonance analysis code, REFIT, and the resonance parameters were determined below 150 eV. It was also discussed the correlations caused by fitting based on statistical uncertainty and correlations for systematic uncertainty based on sample thickness in the transmission measurements.
I and I using ANNRI at MLF/J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 藤 暢輔; 瀬川 麻里子; 前田 亮; 片渕 竜也*
JAEA-Conf 2023-001, p.74 - 79, 2024/02
Measurements to measure the neutron capture cross section of I and I were performed in the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). The time-of-flight (TOF) methodology was employed to determine the neutron capture cross section from thermal to about 100 keV. The results from I were used to normalize the I cross section. Preliminary results of a resonance analysis below 100 eV for I are also presented.
土屋 晴文; 藤 暢輔; 大図 章; 古高 和禎; 北谷 文人; 前田 亮; 米田 政夫
Journal of Nuclear Science and Technology, 60(11), p.1301 - 1312, 2023/11
被引用回数：3 パーセンタイル：62.75(Nuclear Science & Technology)An integrated active neutron non-destructive analysis (NDA) system, Active-N, was developed to gain knowledge of active neutron NDA techniques that are applicable to measurements of nuclear materials in highly radioactive nuclear fuels. Active-N, equipped with a D-T neutron generator, combines three complementary active neutron NDA techniques: Differential Die-away Analysis (DDA), Prompt Gamma-ray Analysis (PGA), and Neutron Resonance Transmission Analysis (NRTA). In this paper, we provide an overview of Active-N and then demonstrate that the compact NRTA system in Active-N can quantify nuclear materials. Monte Carlo simulations were conducted to determine the design of the compact NRTA system including a moderator, flight tubes, and a detector shield. To investigate how accurately the compact NRTA system determines areal densities in a sample, measurements were performed with a Pu pellet-type sample as well as metallic plate samples of In and Ag. The experimental areal densities of 
Pu, 
In and 
Ag were consistent with those calculated for the individual nuclei. These results show that it is feasible to develop a compact NRTA system capable of determining the contents of nuclear materials in nuclear fuels. This research was implemented under the subsidy for nuclear security promotion of MEXT.
古高 和禎; 大図 章; 藤 暢輔
Nuclear Engineering and Technology, 55(11), p.4002 - 4018, 2023/11
被引用回数：1 パーセンタイル：25.62(Nuclear Science & Technology)An integrated neutron interrogation system has been developed for non-destructive assay of highly radioactive special nuclear materials, to accumulate knowledge of the method through developing and using it. The system combines a differential die-away (DDA) measurement system for the quantification of nuclear materials and a prompt gamma-ray analysis (PGA) system for the detection of neutron poisons which disturb the DDA measurements; a common D-T neutron generator is used. A special care has been taken for the selection of materials to reduce the background gamma rays produced by the interrogation neutrons. A series of measurements were performed to test the basic performance of the system. The results show that the DDA system can quantify plutonium of as small as 20~mg and it is not affected by intense neutron background up to 4.2~TBq and gamma ray of 2.2~TBq. As a result of the designing of the combined system as a whole, the gamma-ray background counting rate at the PGA detector was reduced down to 
s
even with the use of the D-T neutron generator. The test measurements show that the PGA system is capable of detecting less than 1~g of boron compound and about 100~g of gadolinium compound in~30 min. This research was implemented under the subsidy for nuclear security promotion of MEXT.
前田 亮; 瀬川 麻里子; 藤 暢輔; 遠藤 駿典; 中村 詔司; 木村 敦
Journal of Radioanalytical and Nuclear Chemistry, 332(8), p.2995 - 2999, 2023/08
被引用回数：0 パーセンタイル：0.00(Chemistry, Analytical)The accuracy of the prompt 
-ray analysis is known to degrade for the samples containing neutron-scattering materials, such as hydrogen, depending on its content. Recently, we discovered that the density of the scattering materials also affects the accuracy. In this paper, we developed a correction method for the effect of the sample densities. The developed correction method is straightforward and applicable to samples with unknown densities. The simulation and experiments verified the performance of the correction method. The results confirmed that the correction method could reduce the uncertainty due to sample density from 47% to approximately 1%.
-ray analysis木下 哲一*; 能任 琢真*; 中島 均*; 小迫 和明*; 加藤 雄大*; 黒岩 洋一*; 倉部 美彩子*; 佐々木 勇気*; 鳥居 和敬*; 前田 亮; et al.
Journal of Radioanalytical and Nuclear Chemistry, 332(2), p.479 - 486, 2023/02
被引用回数：2 パーセンタイル：46.61(Chemistry, Analytical)There are some different chemical and physical forms of water molecules in concretes. Especially, bound water is difficult to determine. In the present work, we determined free + adsorbed water and bound water contained in aggregates and cement pastes, which are component of concretes, by means of conventional gravimetric analysis and prompt -ray analysis (PGA), respectively, in order to evaluate a total water content in concretes. In the PGA, background reduction was attempted by using the time-of-flight (TOF) signal. In addition, the degree of contribution to analytical values by scattered neutrons by samples was evaluated because water would adsorb on the surface of instruments inside the irradiation chamber for the PGA. Contents of the free + adsorbed water and bound water in some geochemical references determined in the present work were compared with the nominal values to confirm the precision. Each water content in aggregates collected from different quarries and cement pastes with different water-to-cement ratios were analyzed. A total water content in young concrete was evaluated on the basis of the analytical values.
米田 政夫; 藤 暢輔
Applied Radiation and Isotopes, 188, p.110391_1 - 110391_6, 2022/10
被引用回数：0 パーセンタイル：0.00(Chemistry, Inorganic & Nuclear)Active neutron methods using pulsed neutrons can measure nuclear materials with higher performance than passive methods. However, previous active neutron methods have not used the observed data effectively. In this study, we developed a new data processing method with higher performance than the conventional method by using time series data. This method is expected to improve the measurement performance through a significant reduction in measurement time and a sensitivity increase compared to the conventional method.
I(n, ) using fast neutron source in the "YAYOI" reactor中村 詔司; 藤 暢輔; 木村 敦; 初川 雄一*; 原田 秀郎
Journal of Nuclear Science and Technology, 59(7), p.851 - 865, 2022/07
被引用回数：1 パーセンタイル：10.00(Nuclear Science & Technology)本研究は、東京大学の高速中性子源炉「弥生」を用いて、評価済み核データライブラリーを検証するために放射化法によりIの積分実験を行った。Iと中性子束モニタを、弥生炉のグローリー孔にて照射した。反応率は、
Iから放出されるガンマ線の収量から求めた。中性子束モニタの反応率の実験値と計算値との比較から、高速中性子スペクトルの確かさを確認した。Iの反応率の実験値を、評価済み核データライブラリーを用いて求めた計算値と比較した。本研究で、評価済みライブラリーJENDL-4.0に採用されている中性子エネルギー10keVから3MeV領域の中性子捕獲断面積データは、18%程、過大評価されていることが分かった。また、本研究の結果は、100keV以下では、Noguere等による報告データを支持した。
-ray analysis前田 亮; 瀬川 麻里子; 藤 暢輔; 遠藤 駿典; 中村 詔司; 木村 敦
Scientific Reports (Internet), 12(1), p.6287_1 - 6287_8, 2022/06
被引用回数：2 パーセンタイル：13.92(Multidisciplinary Sciences)A high-accuracy analytical method is broadly required to obtain reliable research results. Thus, prompt -ray analysis (PGA), one of the most accurate non-destructive analytical methods, has been employed in various fields. However, the measurement accuracy of PGA is also known to degrade in hydrogenous samples. The degradation is caused by variation in the measurement sensitivity (counts per milligram) following the change in neutron energy due to scattering with hydrogen nucleus. Number of scatterings is well known to depend on the hydrogen content in a sample. However, considering multiple scatterings, hydrogen density, which has not been taken into account as yet, may also lead to the accuracy degradation. In this research, the effect of the hydrogen density in PGA is investigated by evaluating the measurement sensitivity of samples with the same hydrogen content and different densities. The results showed that the measurement sensitivity varies by more than 30% depending on the hydrogen density even at the same hydrogen content. The variation is a particularly serious problem for PGA requiring a few percent accuracy in most cases. Additionally, although the variation is apparently observed in hydrogenous samples, the similar phenomenon can occur in other nuclides with a large scattering cross section; it may affect nuclear cross-section measurements using neutrons in such fields as astrophysics and nuclear energy.
瀬川 麻里子; 藤 暢輔; 甲斐 哲也; 木村 敦; 中村 詔司
Annals of Nuclear Energy, 167, p.108828_1 - 108828_5, 2022/03
被引用回数：1 パーセンタイル：14.76(Nuclear Science & Technology)To obtain accurate analytical results via neutron-capture reactions, the effects of sample shapes must be considered. However, the estimations of the effects were difficult to verify in some cases such as sealed samples and valuable objects. In this study, the shape effects for sealed radioactive samples were estimated experimentally. The significant localization of the I sample was confirmed only by an energy-resolved neutron imaging. It is revealed that the shape effect was necessary to be corrected at the neutron resonance peaks. Consequently, we conclude that the energy-resolved neutron imaging will be quite effective to improve the analytical accuracy.
遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 寺田 和司*; 明午 伸一郎; 藤 暢輔; 瀬川 麻里子; et al.
Journal of Nuclear Science and Technology, 59(3), p.318 - 333, 2022/03
被引用回数：9 パーセンタイル：67.14(Nuclear Science & Technology)In order to improve the accuracy of the cross-section and the resonance parameters of 
Nb, neutron capture and total cross-sections were measured using the J-PARC MLF ANNRI. The thermal-neutron capture cross-section was deduced as 0.970.12 b. The resonance parameters of 11 resonances below 400 eV were determined from obtained capture cross-sections and transmission ratios by using the resonance analysis code, REFIT.
中村 詔司; 初川 雄一*; 木村 敦; 藤 暢輔; 原田 秀郎
Journal of Nuclear Science and Technology, 58(12), p.1318 - 1329, 2021/12
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)本研究は、東大の高速中性子源炉「弥生」を用いて、放射化法により
Tcの積分実験を行った。Tc試料を、気送管システムを用いて照射した。Tcの反応率は、
Tcから放出されるガンマ線を測定して求めた。中性子束は、Au箔を用いてモニタした。本研究におけるTcの反応率の結果は、JENDL-4.0を支持した。
米田 政夫; 藤 暢輔; 田辺 鴻典*; 北村 康則*; 三澤 毅*
Annals of Nuclear Energy, 159, p.108300_1 - 108300_8, 2021/09
被引用回数：4 パーセンタイル：40.86(Nuclear Science & Technology)The rotation method is a novel method for detecting nuclear materials using a neutron source such as californium. In this method, while a neutron source is rotated rapidly nearby a measurement object, neutron measurement is carried out by synchronizing the rotation motion. If the object contains a nuclear material, as the rotation speed increases, the larger deformation of time distribution of neutron counts is observed, which in turn resulted to the detection of the nuclear material. In addition to its features of low cost and portability, this method is capable of detecting uranium that emits very few spontaneous fission neutrons. This study presents the fundamental principle of this method and its effectiveness for detecting nuclear materials through the experimental verifications.
古高 和禎; 大図 章; 藤 暢輔
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 9 Pages, 2021/08
We have been developing an integrated active neutron non-destructive analysis system for highly radioactive nuclear materials, "Active-N", using an intense D-T neutron source. The system is composed of the following mutually complementing different measurement systems: Differential Die-away Analysis (DDA), Neutron Resonance Transmission Analysis (NRTA), and Prompt Gamma-ray Analysis (PGA). The former two are for measurements of total amount of fissile material and of isotopic composition, respectively. The purpose of the last one, i.e. PGA measurement system is the detection of explosives contained in e.g., dirty bombs and of chemical warfare agents, as well as of neutron poisons which absorb neutrons and disturb DDA measurements. This report describes mainly the PGA measurement system. In the PGA measurement system, to resolve individual gamma-ray peaks, a Ge detector is utilized. It is well known that irradiation of fast neutrons (
keV) to Ge detectors cause damages to the detectors and gradually worsen their resolution, and finally make them unusable without a laborious treatment. Therefore, it is essential to shield the PGA detector against the neutrons from the D-T neutron generator. In addition, to reduce background gamma rays from the materials used for the DDA system, they should also be carefully chosen. In order to design an appropriate neutron shield for the PGA measurement system and diminish the sources of the background gamma rays, simulation study was done using a particle transport code system PHITS. Based on the results, a shielding for the PGA measurement system has been designed which reduces the number of damaging neutrons by an order of magnitude. The Active-N system which incorporates the PGA measurement system equipped with the neutron shielding, has been installed at NUCEF facility in JAEA Tokai. This research was implemented under the subsidy for nuclear security promotion from MEXT.
藤 暢輔; 大図 章; 土屋 晴文; 古高 和禎; 北谷 文人; 米田 政夫; 前田 亮; 小泉 光生
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 8 Pages, 2021/08
Since neutrons have exceptional ability to penetrate high-density materials and can induce fission, they are used in non-destructive analysis such as, Differential Die-Away Analysis (DDA), Prompt Gamma-ray Analysis (PGA) and Neutron Resonance Transmission Analysis (NRTA). The different analytical methods give us complementary information, which are particularly useful for the quantification of Special Nuclear Materials in highly radioactive nuclear materials, including spent fuel. The Japan Atomic Energy Agency (JAEA) and the Joint Research Centre (JRC) of the European Commission are collaborating to develop an active neutron NDA system for nuclear non-proliferation and nuclear security. In the second phase of the project, an integrated active neutron NDA system: Active-N which enables the simultaneous measurements of DDA, PGA and NRTA has been developed. The DDA detects fission neutrons, and it can determine small amounts of the fissile mass. PGA is utilized for the quantification of neutron absorber and particularly useful for the detection of explosives. NRTA can be used to quantify almost all medium and high-Z elements and considered as one of the most accurate NDA. In this presentation, we will provide an overview of Active-N and report the recent experimental results. This research was implemented under the subsidy for nuclear security promotion of MEXT: Ministry of Education, Culture, Sports, Science and Technology.
Pd and Tc藤 暢輔; 瀬川 麻里子; 前田 亮; 常山 正幸*; 木村 敦; 中村 詔司; 遠藤 駿典; 海老原 充*
Analytical Chemistry, 93(28), p.9771 - 9777, 2021/07
被引用回数：7 パーセンタイル：38.51(Chemistry, Analytical)Considering the expanding demand for nuclear waste management of the spent nuclear fuel materials in near future, a non-destructive analytical scheme applicable to the most difficult-to-measure nuclide of Pd, which emits no decay gamma-rays and whose half-life is too long to be decayed out during a human lifetime, was designed. The scheme consists of a sophisticated instrument capable of the detection of gamma-rays by Ge detectors coupled with time-of-flight measurement of neutrons and a high-intensity pulsed neutron beam, and can simultaneously perform TOF-coupled prompt gamma-ray analysis (TOF-PGA) as well as PGA and NRCA. An analytical capability was evaluated by applying to simulated samples of the Tc-platinum group metals (Tc-PGMs) obtained by the group partitioning process of spent nuclear fuels, which contain not only Pd but also Tc and another difficult-to-measure fission product. It was confirmed that, although PGA and NRCA could accurately analyze both nuclides in individual single substances, only TOF-PGA can analyze Pd as well as Tc in the Tc-PGMs simulated sample. The TOF-PGA measurement technique can be widely used for the non-destructive analysis of Pd and Tc in nuclear wastes.
