Implementation of ideal cascade model for uranium enrichment to nuclear fuel cycle simulator

阿部 拓海; 鈴木 大河*; 岡村 知拓*; 中瀬 正彦*

Annals of Nuclear Energy, 232, p.112224_1 - 112224_7, 2026/07

https://doi.org/10.1016/j.anucene.2026.112224

Reprocessed uranium is important for sustainable nuclear fuel use. It contains isotopes such as U-232, U-234, and U-236, which influence enrichment and later nuclear fuel cycle steps. To evaluate these effects, nuclear fuel cycle simulators require cascade models capable of handling multi-isotopic uranium. In this study, an ideal cascade model based on the matched abundance ratio cascade was implemented in a nuclear fuel cycle simulator NMB4, developed by the Institute of Science Tokyo and Japan Atomic Energy Agency. A three-component approximation was introduced to simplify calculations. Validation against numerical solutions and experimental data showed good agreement. Compared with the simple coefficient method, the ideal cascade model improved predictions for isotopes such as U-232 and U-236, which affect radiation, separative work, and actinide production. These results demonstrate that the new model enhances the accuracy of reprocessed uranium evaluation, aiding future fuel cycle planning.

Uncovering hidden dispersion patterns of radioactive cesium-rich microparticles from Fukushima Daiichi

宮崎 加奈子*; 笛田 和希*; 門脇 正尚; 寺田 宏明; 香西 直文; 岩田 孟; 堀江 憲路*; 竹原 真美*; 山崎 信哉*; Grambow, B.*; et al.

Journal of Hazardous Materials, 511, p.142180_1 - 142180_17, 2026/06

https://doi.org/10.1016/j.jhazmat.2026.142180

Radioactive cesium-rich microparticles (CsMPs) released from the Fukushima Daiichi Nuclear Power Plant (FDNPP) in 2011 pose a persistent environmental concern, yet their initial atmospheric dispersion has remained poorly constrained. To elucidate their release dynamics, we quantified CsMPs in 100 surface soil samples collected across Fukushima Prefecture in July 2011. CsMP abundance and radioactive fraction (RF) ranged from 0 to 52,300 particles kg; (dry weight) and 0-61.85% of deposited Cs, respectively. Integrating these results with WSPEEDI atmospheric simulations reveals a major formation event of CsMPs around 03:00 JST on 15th March 2011. The plume emitted at this time was heavily enriched in CsMPs, whereas plumes released after 00:00 JST on 16th March 2011 contained no detectable CsMPs, indicating that particle formation had ceased by then. The widespread distribution of CsMPs across Fukushima Prefecture is therefore attributed primarily to this single plume on 15th March 2011. Directional differences in CsMP abundance reflect temporal variations in CsMP density within the plume, with maximum estimated concentrations of 2,070 particles m; toward the southwest and 4,700 particles m; toward the northwest. Additionally, elevated CsMP densities coupled with relatively low RF in the northwest suggest supplementary deposition of water-soluble cesium between 17:00 and 23:00 JST on 15 March. These findings constrain the timing and mechanisms of CsMP formation and dispersion, providing essential insights for environmental reconstruction and future radiological risk assessment.

Evaluation of residual stress distribution in linear friction welded steel joint neutron diffraction mapping measurement

山下 享介*; 柳樂 知也*; Gong, W.; 川崎 卓郎; Harjo, S.; 潮田 浩作*; 藤井 英俊*

ISIJ International, 66(5), p.673 - 684, 2026/04

https://doi.org/10.2355/isijinternational.ISIJINT-2025-405

In this study, neutron diffraction mapping was performed on linear friction welded (LFW) joints of 12 mm thick high-phosphorus weathering steel (SPA-H) to evaluate residual stress, dislocation density, and crystallographic orientation. Welding was conducted under applied pressures of 100 and 250 MPa. The weld interface mainly consisted of refined ferrite with minor retained austenite and martensite, indicating reverse transformation to austenite during welding. The 250 MPa condition resulted in a lower welding temperature. Elongated grains were observed near the surface along the oscillation direction, while equiaxed grains appeared at the center. Both joints showed high tensile residual stresses at the weld center and compressive stresses near the surface. Higher applied pressure increased dislocation density because of suppressed dynamic recovery. Strong texture formation due to plastic flow was observed, while the effect of applied pressure on texture development was limited.

Strengthening mechanism in ferrite and austenite of friction stir welded duplex stainless steel; neutron diffraction study

山下 享介*; 小山 元道*; Gong, W.; 川崎 卓郎; Harjo, S.; 潮田 浩作*; 藤井 英俊*

ISIJ International, 66(4), p.477 - 488, 2026/03

https://doi.org/10.2355/isijinternational.ISIJINT-2025-291

This study investigated strengthening mechanisms in friction stir welded (FSW) duplex stainless steel (DSS) using in situ neutron diffraction during tensile testing. Two welding conditions, FSW300 and FSW600, produced significant grain refinement, with grains below 1 m in FSW300. Both conditions increased yield and tensile strength but reduced elongation compared with the base metal (BM), while FSW300 retained higher total elongation than FSW600. Neutron diffraction revealed that was the harder phase in the BM, whereas became the harder phase after FSW. Phase stress analysis showed that was more sensitive to grain refinement strengthening, shifting the dominant strengthening contribution from to . Although stacking faults in increased after FSW, work hardening of decreased, while showed enhanced texture development and dislocation accumulation.

Facile preparation of antiviral grafted fabrics based on silver-immobilized phosphate groups and evaluation of COVID-19 infections

松村 大樹; 辻 卓也; 瀬古 典明*; 他5名*

Journal of Radioanalytical and Nuclear Chemistry, 335(2), p.1543 - 1552, 2026/02

https://doi.org/10.1007/s10967-025-10608-y

The COVID-19 pandemic has underscored the need for protective materials with rapid and durable antiviral properties. We developed silver (Ag)-immobilized fabrics via radiation-induced graft polymerization and tested their activity against SARS-CoV-2. The fabrics reduced 40,000 viral particles to below detection within one hour, showed no Ag leaching after 24 h in water, and retained complete antiviral performance after one year of storage. These findings demonstrate the long-term stability and strong potential of Ag-immobilized fabrics for industrial use in protective equipment.

Induction of large in-plane uniaxial magnetic anisotropy for Co-Fe-B-Pt thin films by magnetic field annealing

山崎 匠*; 石谷 優剛*; 中田 勝之*; 佐々木 智生*; 遠藤 恭*; 高梨 弘毅; 関 剛斎*

Journal of Applied Physics, 138(23), p.233905_1 - 233905_11, 2025/12

https://doi.org/10.1063/5.0300010

The induction of large in-plane uniaxial magnetic anisotropy for the CoFeB-based thin films by post-annealing under the magnetic field application is reported. The comprehensive study reveals the influence of CoFeB composition and Pt addition to CoFeB on the induced magnetic anisotropy by magnetic field annealing. The addition of Pt to a CoFeB film significantly enhances the effect of magnetic field annealing, and as a result, the CoFeB-Pt films exhibit the in-plane uniaxial magnetic anisotropy energies that are one order of magnitude larger than the pristine CoFeB films. In order to understand the mechanism of magnetic anisotropy induction by post-annealing, the magnetostriction measurement for the CoFeB-based thin films were carried out. The correlation between the induced magnetic anisotropy and magnetoelastic properties is discussed.

中性子回折マッピング測定法を用いた線形摩擦接合鋼継手の残留応力分布評価

山下 享介*; 柳樂 知也*; Gong, W.; 川崎 卓郎; Harjo, S.; 潮田 浩作*; 藤井 英俊*

鉄と鋼, 111(17), p.1057 - 1071, 2025/12

https://doi.org/10.2355/tetsutohagane.TETSU-2025-042

Neutron diffraction mapping was conducted on linear friction welded joints of 12 mm thick high-phosphorus weathering steel (SPA-H) to evaluate residual stress, dislocation density, and crystallographic orientation. Welding was performed at 100 MPa and 250 MPa. The weld interface mainly comprised refined ferrite with retained austenite and martensite, indicating temperatures exceeded A1 and induced reverse transformation. The 250 MPa joint showed a lower welding temperature. Elongated grains formed near the surface along the oscillation direction (OD), while equiaxed grains appeared at the center. High tensile residual stresses were found at the weld center, with compressive stress near the surface perpendicular to the weld. Pressure had little effect on overall stress trends. Dislocation density increased with pressure due to suppressed dynamic recovery. Strong texture developed at the interface, with limited pressure dependence.

Actinide separation by column method using polyvinylpolypyrrolidone

和田 一真*; 風間 裕行*; 阿部 千景*; 大西 貴士; 山本 昌彦; 田口 茂郎; 久野 剛彦; 前田 宏治; 出光 一哉*; 鈴木 達也*

Journal of Radioanalytical and Nuclear Chemistry, 334(11), p.8961 - 8968, 2025/11

https://doi.org/10.1007/s10967-025-10539-8

市販のポリビニルポリピロリドン(PVPP)を質量分析の前処理として用いてアクチニドの分離を検討した。アクチニドとしては、ウラン、トリウム及びプルトニウムを用いた。硝酸中での吸着試験を行い、An(IV)とAn(VI)の吸着データを得た。また、PVPPを用いたカラム分離法により、An(III)/An(IV)/An(VI)の相互分離に成功した。さらに、炭酸イオンの導入により、U(VI)の溶出効率が向上した。本法は、アクチニドの質量分析のための相互分離法として応用できる可能性がある。

Phase transitions and relaxor behavior of lead-free ferroelectric bismuth potassium titanate

斎藤 幸太郎*; 松尾 拓紀*; 米田 安宏; Ye, Z.-G*; 野口 祐二*

Journal of Applied Physics, 138(9), p.094102_1 - 094102_9, 2025/09

https://doi.org/10.1063/5.0272995

The phase transition behavior of relaxor ferroelectric BiKTiO (BKT) is investigated in ceramic from based on synchrotron radiation X-ray diffraction measurements and dielectric measurements as a function of temperature. The structural transformation from the cubic non-ergodic (NER) relaxor state to the tetragonal NER state triggers the spontaneous relaxor-to-ferroelectric phase transition. Based on the experimental observations, a temperature phase diagram of BKT is established in terms of average crystal structure and polar order.

非接触測定法を用いた燃料デブリ臨界解析技術の高度化(委託研究); 令和5年度英知を結集した原子力科学技術・人材育成推進事業

廃炉環境国際共同研究センター; 東京科学大学*

JAEA-Review 2025-010, 62 Pages, 2025/08

JAEA-Review-2025-010.pdf:3.63MB

日本原子力研究開発機構(JAEA)廃炉環境国際共同研究センター(CLADS)では、令和5年度英知を結集した原子力科学技術・人材育成推進事業(以下、「本事業」という。)を実施している。本事業は、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の廃炉等をはじめとした原子力分野の課題解決に貢献するため、国内外の英知を結集し、様々な分野の知見や経験を、従前の機関や分野の壁を越えて緊密に融合・連携させた基礎的・基盤的研究及び人材育成を推進することを目的としている。平成30年度の新規採択課題から実施主体を文部科学省からJAEAに移行することで、JAEAとアカデミアとの連携を強化し、廃炉に資する中長期的な研究開発・人材育成をより安定的かつ継続的に実施する体制を構築した。本研究は、令和3年度に採択された研究課題のうち、「非接触測定法を用いた燃料デブリ臨界解析技術の高度化」の令和3年度から令和5年度分の研究成果について取りまとめたものである。本研究は、非接触のアクティブ中性子法により燃料デブリの臨界安全上の特性を評価する測定システムの開発と、燃料デブリ取り出し作業員の安全確保方策の確立に資する基盤技術として多領域積分型動特性解析コードの開発により燃料デブリ臨界解析技術を高度化することを目的としており、東京科学大学、東京都市大学、産業技術総合研究所、長岡技術科学大学が連携して実施した。燃料デブリの臨界特性システムの開発・性能評価では、ポリエチレン減速材とHe比例計数管から構築される2層構造の検出器を開発し、検出器の動作検証及び性能試験を実施した。開発した検出器を用いて得られる測定データから燃料デブリに含まれる核分裂核種量、水素含有量、臨界安全上の特性を導出するための手法を検討・評価し、検出限界、精度、適応可能なデブリ形状を評価した。燃料デブリ弱結合炉体系臨界影響評価手法の高度化では、本研究を通じて、遅発中性子による核分裂の効果を考慮することができ、燃料デブリの動きにも対応可能なMIK2.0-MVPコードの基本機能を開発した。MIK2.0-MVPコードは、C()関数のタリー計算を並列化すれば、スパコンを活用することによって、燃料デブリ多粒子体系を含む弱結合炉体系のような複雑な体系であっても、粒子法との弱連成計算の範囲内で、動特性計算が実行可能となる見通しを得た。