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value ratios for off-site transportation of small-amount of fuel debris retrieved from the Fukushima Daiichi Nuclear Power Station坂本 雅洋; 奥村 啓介; 神野 郁夫; 松村 太伊知; Riyana, E. S.; 寺島 顕一; 金子 純一*; 溝上 暢人*; 溝上 伸也*
Radioisotopes, 75(S-01), p.S-001_1 - S-001_5, 2026/04
In the Unit 2 of TEPCO's Fukushima Daiichi Nuclear Power Station (1F), trial retrievals of fuel debris with small-amount is underway. The retrieved fuel debris will be transported out of 1F site to Institutes in Ibaraki prefecture for analysis. The analyzed results will be utilized as feedback for the improvement of the processes (retrieval, transportation and storage) in the fuel debris management, and also for the development of technologies necessary in the future. The weight of fuel debris in the first trial retrieval was about 0.7 g. After several retrieval trials planned, the scale of retrieval will be expanded step by step in the future. In the retrieval, a rational transportation container should be considered beforehand, following the laws and regulations associated with the off-site transportation. The transportation container should be chosen based on radioactivity limit A or A value ratios: hazardous dose exposure will be prevented in case of container failure with the A value (considering the external exposure) and the A value (considering both the external and internal exposures). We estimated the radioactivity of the retrieved fuel debris using the results of the detailed nuclide inventory calculation. With a numerical analysis of the A and A value ratios, we confirmed the applicability of the Type A transport container for the retrieved small-amount fuel debris.
神野 郁夫; 奥村 啓介; 松村 太伊知; Riyana, E. S.; 寺島 顕一; 坂本 雅洋
Progress in Nuclear Science and Technology (Internet), 8, p.343 - 346, 2025/09
福島第一原子力発電所2号機のシールドプラグ隙間のCs-137汚染分布をオペレーションフロアから測定するために、ガンマ線ピンホールカメラを用いる方法を提案する。決定論的計算により、可能性を議論する。
坂本 雅洋; 奥村 啓介; 神野 郁夫; 松村 太伊知; 寺島 顕一; Riyana, E. S.; 金子 純一*; 溝上 暢人*; 溝上 伸也*
Journal of Nuclear Science and Technology, 62(8), p.756 - 765, 2025/08
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)In this paper, we propose a new nuclide inventory estimation method based on computational methods, called a "theoretical scaling factor method" for difficult-to-measure (DTM) nuclides in fuel debris and radioactive wastes. The theoretical scaling factor method provides a method similar to a conventional scaling factor method. The theoretical scaling factor method, however, does not require performing many measurements to obtain correlations between a key nuclide which is easy-to-measure and a DTM nuclide. Instead of actual analytical measurements, the results of theoretical calculations are used. A correlation equation between the key nuclide and the DTM nuclide is created based on the results of theoretical calculations, and the DTM nuclide is deterministically estimated using the measurement value of the key nuclide only. In this paper, we selected Cs-135 as the DTM nuclide and Cs-137 as the key nuclide. Cs-135 has a long half-life of 2.3
10
years and is one of the important fission products in the safety evaluation for the geological disposal of high-level radioactive waste, because it dissolves and migrates in groundwater easily. We confirmed the validity of the proposed method using measured data of Cs-137 and Cs-135 on radioactive wastes from the Fukushima Daiichi Nuclear Power Station (1F) accident obtained by many researchers. It can be used as a rational and efficient technology to reduce the analysis costs of various types of fuel debris and radioactive waste present at 1F.
坂本 雅洋; 奥村 啓介; 神野 郁夫; 松村 太伊知; 寺島 顕一; Riyana, E. S.; 溝上 暢人*; 溝上 伸也*
JAEA-Research 2024-017, 14 Pages, 2025/03
JAEA-Research-2024-017.pdf:1.34MB
東京電力ホールディングス株式会社福島第一原子力発電所では、2号機から燃料デブリの試験的取り出しを行い、回収物を構外輸送し茨城地区で分析することが計画されている。取り出された燃料デブリの分析結果は、将来的な燃料デブリ管理の各工程(取り出し、収納、移送、保管等)の検討にフィードバックされ、必要な技術開発に活用することが期待されている。試験的取り出しでサンプリングされる燃料デブリは数グラム程度が予定されており、その後、段階的に取り出し規模を拡大させていくことになる。試験的取り出しにおいては、構外輸送に係る関係法令に則って事前に合理的な輸送容器を検討することが必要になる。本報では物質組成や性状が不明瞭な燃料デブリ回収物の安全評価に資するため、少量燃料デブリの構外輸送に向けたA型輸送容器の適用性評価を行った。
松村 太伊知; 奥村 啓介; 坂本 雅洋; 寺島 顕一; Riyana, E. S.; 近藤 千博*
Nuclear Engineering and Design, 432, p.113791_1 - 113791_9, 2025/02
被引用回数：3 パーセンタイル：49.06(Nuclear Science & Technology)Retrieving objects with a small amount of fuel debris, such as a few grams, will begin soon at the Fukushima Daiichi Nuclear Power Station (1F) at the start of decommissioning. Objects retrieved from the primary containment vessel are not necessarily fuel debris; fuel debris is an object from which neutrons are emitted because it contains nuclear-fuel material. However, the characteristics of the neutrons emitted by fuel debris are unknown. Fuel debris was categorized into five types according to the elapsed time from the accident, burnup, and fuel type (UO or mixed oxide). The number and energy spectra of (
, 
) and spontaneous fission neutrons emitted from 1 g of each fuel debris type were estimated using the SOURCES 4C code to obtain the neutron characteristics. The results showed that the average neutron energy is approximately 2.1 MeV, regardless of the type of fuel debris. However, the intensities of neutrons emitted from the fuel debris in 1F Units 2 and 3 varied by four orders of magnitude according to the fuel debris type.
Riyana, E. S.; 奥村 啓介; 坂本 雅洋; 松村 太伊知; 寺島 顕一; 神野 郁夫
Journal of Nuclear Science and Technology, 61(2), p.269 - 276, 2024/02
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)We investigated the possibility of estimating the effective neutron multiplication factor (
) of the fuel debris inside the canister and primary containment vessel (PCV) of Unit 2 of the Fukushima Daiichi Nuclear Power Station (1F) using remote gas-radioactivity measurement via simulation-based calculations. Our results demonstrate an almost linear correlation between and the 
Kr-to-
Xe activity ratio with respect to various fuel debris compositions. This correlation is maintained regardless of geometries such as the fuel debris canister and the PCV.
-rays of fuel debris松村 太伊知; 奥村 啓介; 藤田 学*; 坂本 雅洋; 寺島 顕一; Riyana, E. S.
Radiation Physics and Chemistry, 199, p.110298_1 - 110298_8, 2022/10
被引用回数：3 パーセンタイル：28.30(Chemistry, Physical)The characterization of bremsstrahlung and -rays from fuel debris differs from that of spent fuels evaluated to date, due to factors such as material composition and release of volatile fission products. In this work, in order to clarify the conditions under which the effect of bremsstrahlung compared to the total photons (bremsstrahlung and -rays) in fuel debris is maximized, the average energies and dose rates from the energy spectra of bremsstrahlung and -rays on the fuel debris surface were obtained using a Monte Carlo simulation. In the simulation, the average energies and dose rates were evaluated with consideration of the composition, size, fission product release, and retrieval time of the fuel debris. The simulation showed that the composition with the largest amount of change to the average total photons energy caused by bremsstrahlung was the molten fuel debris, and the composition with the maximum fraction of bremsstrahlung in the dose rate was the UO. The maximum value of the fraction of bremsstrahlung in the dose rate was evaluated to be about 17%. This work is expected to contribute to the prediction of the radiation characteristics of the fuel debris that will be retrieved from the Fukushima Daiichi Nuclear Power Station in the near future.
Riyana, E. S.; 奥村 啓介; 坂本 雅洋; 松村 太伊知; 寺島 顕一
Journal of Nuclear Science and Technology, 59(4), p.424 - 430, 2022/04
被引用回数：1 パーセンタイル：6.81(Nuclear Science & Technology)Modification of the Monte Carlo depletion calculation code OpenMC was performed to enable the depletion calculation of the subcritical neutron multiplying system. With the modified code, it became possible to evaluate the quantity of short half-life fission products from spontaneous and induced fissions in the subcritical system. As a preliminary study, it was applied to the fuel debris storage canister filled with nuclear materials and spontaneous fission nuclides. It was confirmed that the code could successfully provide a quantity of short half-life FPs over time and provide the relationship between the activity ratio of Kr-88 to Xe-135 and effective neutron multiplication factor of the canister.
寺島 顕一; 奥村 啓介
Journal of Advanced Simulation in Science and Engineering (Internet), 8(1), p.73 - 86, 2021/03
In 2021, fuel debris samplings are planned to start as part of a step-by-step process at the Fukushima Daiichi nuclear power station. The dose rate of the fuel debris for safety treatments of the fuel debris should be predicted. However, various elements are mixed in the fuel debris, and thus predicting the dose rate will be challenging. Therefore, we conducted a large number of Monte Carlo radiation transport simulations for cases where parameters such as fuel debris size, composition, and density were significantly changed. Consequently, we obtained a simple and analytical formula that can predict the dose rate using a minimum number of parameters.
Riyana, E. S.; 奥村 啓介; 寺島 顕一; 松村 太伊知; 坂本 雅洋
Mechanical Engineering Journal (Internet), 7(3), p.19-00543_1 - 19-00543_8, 2020/06
Prediction of the fuel debris location and distribution inside the primary containment vessel (PCV) of the Fukushima Daiichi Nuclear Power Plant is important to decide further decommissioning step and strategy. The radiation measurements in the past internal investigations have not yet provided enough information to predict fuel debris location and its distribution inside PCV. To support further measurement efforts, we simulate the detector response inside the PCV. The calculation result could provide a base on deciding suitable detector systems to assist the efforts on searching, localizing and defining distributions of the fuel debris.
Riyana, E. S.; 奥村 啓介; 寺島 顕一
Journal of Nuclear Science and Technology, 56(9-10), p.922 - 931, 2019/09
被引用回数：11 パーセンタイル：63.60(Nuclear Science & Technology)Determination of fuel debris location and distribution inside primary containment vessel of Fukushima Daiichi Nuclear Power Station is important to decide further decommissioning step and strategy. We calculate neutron flux produced from fuel debris and secondary particles photon resulted from neutron reaction with nuclides inside fuel debris, including direct photon emission from FPs in fuel debris. Neutron and gamma characteristics resulted from calculation could be use as basis for determination suitable spectrometer system or detector for searching, localizing and treatment of fuel debris.
Riyana, E. S.; 奥村 啓介; 寺島 顕一
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 4 Pages, 2019/05
Determination of fuel debris location and distribution inside primary containment vessel (PCV) of Fukushima Daiichi Nuclear Power Station is important to decide further decommissioning step and strategy. Past measurements not yet provide enough information to determine fuel debris location and its distribution inside PCV. To support further measurements effort, we simulate detector response inside PCV based on calculated photon and neutron emission spectrum produced from fuel debris. The Calculation result could be use as basis for determination of suitable spectrometer system or detector for search, localized, define fuel debris distributions and treatment of fuel debris.
岩崎 悠真*; 竹内 一郎*; Stanev, V.*; Gilad Kusne, A.*; 石田 真彦*; 桐原 明宏*; 井原 和紀*; 澤田 亮人*; 寺島 浩一*; 染谷 浩子*; et al.
Scientific Reports (Internet), 9, p.2751_1 - 2751_7, 2019/02
被引用回数：104 パーセンタイル：94.65(Multidisciplinary Sciences)Thermoelectric technologies are becoming indispensable in the quest for a sustainable future. Recently, an emerging phenomenon, the spin-driven thermoelectric effect (STE), has garnered much attention as a promising path towards low cost and versatile thermoelectric technology with easily scalable manufacturing. However, progress in development of STE devices is hindered by the lack of understanding of the fundamental physics and materials properties responsible for the effect. In such nascent scientific field, data-driven approaches relying on statistics and machine learning, instead of more traditional modeling methods, can exhibit their full potential. Here, we use machine learning modeling to establish the key physical parameters controlling STE. Guided by the models, we have carried out actual material synthesis which led to the identification of a novel STE material with a thermopower an order of magnitude larger than that of the current generation of STE devices.
(As
P
)笠原 成*; Shi, H. J.*; 橋本 顕一郎*; 利根川 翔*; 水上 雄太*; 芝内 孝禎*; 杉本 邦久*; 福田 竜生; 寺嶋 孝仁*; Nevidomskyy, A. H.*; et al.
Nature, 486(7403), p.382 - 385, 2012/06
被引用回数：415 パーセンタイル：99.13(Multidisciplinary Sciences)The electron nematicity, which break rotational symmetry of the crystal lattice, has been recently observed in high-
superconductors. In iron-pnictides, it has been associated with the tetragonal-to-orthorhombic structural transition at 
, and the observations has been limited in the orthorhombic phase or in the tetragonal phase under uniaxial strain. In this investigation we provide magnetic torque measurements, a thermodynamic evidence which clearly shows the development of nematicity well above and the persistence in the nonmagnetic superconducting regime. Combined with synchrotron X-ray measurements, our results identify two distinct temperatures-one at 
, signifying a true nematic transition, and the other at (
), which we show to be not a true phase transition, but rather what we refer to as a "meta-nematic transition", in analogy to the well-known metamagnetic transition in the theory of magnetism.
Riyana, E. S.; 坂本 雅洋; 松村 太伊知; 寺島 顕一; 奥村 啓介
no journal, ,
We investigated the possibility of estimating the effective neutron multiplication factor (keff) of the fuel-debris inside the primary containment vessel (PCV) of unit-2 of Fukushima Daiichi Nuclear Power Station (1F) using remote gas-radioactivity measurement. Our calculation result demonstrates the correlation between keff and the activity ratio (AR) of Kr-to-Xe for various fuel debris compositions and geometry. We also show the time-dependent behavior of the AR of Kr-to-Xe when the keff changes suddenly in PCV.
Riyana, E. S.; 坂本 雅洋; 松村 太伊知; 寺島 顕一; 奥村 啓介
no journal, ,
We investigated the possibility of estimating the effective neutron multiplication factor (k
) of the fuel-debris canister using remote gas-radioactivity measurement. The fuel-debris compositions inside a canister may vary and depend on the fuel-debris location inside the primary containment vessel and fuel-debris removal process. Our calculation result demonstrates the correlation between k and the activity ratio of Kr-to-Xe for the various fuel debris material conditions such as fuel burn-up degree before the accident of the Fukushima Daiichi Nuclear Power Stations (1F), canister filling rate, water fraction, and fuel-debris type.
Srの分布測定のための少量試料中Srの測定小荒井 一真; 松枝 誠; 青木 譲; 柳澤 華代*; 藤原 健壮; 寺島 元基; 木野 康志*; 岡 壽崇; 奥津 賢一*; 山下 琢磨*; et al.
no journal, ,
硬組織(歯や骨)は動物の生息環境中のSrの分布の指標とされている。硬組織は代謝の遅い生体組織であるため、組織内に生体のSr取り込みの履歴を残す可能性がある。硬組織内でのSrの分布を明らかにするためには、硬組織を分割し微細な試料の測定が求められる。本発表では、少量試料に有利なICP-MS法の妥当性を明らかにするために、放射能測定法との比較を行った。放射能測定法およびICP-MS法ともに0.10g中の硬組織中Srの定量に成功した。LODを比較すると、1.0g試料の放射能測定が最も低く、続いて0.10g試料のICP-MS測定、0.10gの放射能測定が最も大きいという結果であった。またICP-MS法の分析時間は8時間と、放射能測定法より短時間での分析である。硬組織の微細な破片を測定する場合、ICP-MS法は放射能測定法同様に、Sr分析法として適用可能であると考えられる。今後、定量値のばらつきや検出感度を改善することで、より実用的な生体のSr取り込み履歴の調査に応用できると考えられる。
Csの理論的スケーリングファクタの開発寺島 顕一; 坂本 雅洋; 松村 太伊知; 奥村 啓介; 藤田 学*
no journal, ,
Csは地層処分の安全性評価において、放射能インベントリ評価が重視される難分析超寿命FP核種の1つであり、福島第一原子力発電所の事故に起因する放射性廃棄物や燃料デブリ等にも含まれている。従来の使用済み燃料や放射性廃棄物と大きく異なる点は、燃焼履歴が異なる広範囲な燃焼度の原子炉燃料が事故時に高温溶融してCsの多くが揮発したことである。また、従来のスケーリングファクタ法のように、分析結果を蓄積して統計的に相関式を得る方法は、燃料デブリや高線量Cs汚染物の場合には時間と費用を要し得策ではない。この問題を解決するため、測定が比較的容易な
Cs量から、揮発や混合を考慮した理論に基づきCs量を精度よく評価するための理論的スケーリングファクタ法を提案する。
寺島 顕一; 坂本 雅洋; 松村 太伊知; 冠城 雅晃; Riyana, E. S.; 能見 貴佳; 奥村 啓介
no journal, ,
福島第一原子力発電所(1F)の格納容器内のような高ガンマ線環境下での燃料デブリ探査や、回収物中の核燃料物質の有無を判断するための手法開発を進めている。その中で、自発核分裂や誘起核分裂などに起因する僅かな中性子を、狭隘空間かつ高ガンマ線環境下で検出する手法として、中性子の積算線量計であるバブルディテクター(BD)に着目した。BDはガンマ線に不感で、小型軽量,目視確認可能,外部電源やケーブル不要といった特長を有している。そこで、BDに対するコバルト60を用いたガンマ線照射試験、ならびにMOX燃料を用いた中性子検出試験を実施した。その結果、速中性子用のBDは10.0kGyまでの高ガンマ線場で利用できること、及びMOX燃料由来の中性子を検出できることを確認した。
坂本 雅洋; 寺島 顕一; 松村 太伊知; 藤田 学*; 奥村 啓介
no journal, ,
福島第一原子力発電所事故で発生した燃料デブリがどの程度の崩壊熱を出しているか把握しておくことは、今後のデブリ取出しに向けて冷却方法の検討やデブリ輸送・保管容器の除熱評価において重要である。しかし、燃料デブリは燃焼履歴が明確な使用済み燃料のように核種組成が明らかでないため、崩壊熱の評価は容易ではない。そこで本研究ではデブリの重量, 燃焼度, 核種の放出率, 評価時期などのパラメータを考慮した多種多様なデブリの崩壊熱を容易に計算する手法を開発した。
