Development of phenomenological degradation models for Cr-Coated Zr alloy cladding under high-temperature oxidation conditions

谷口 良徳; Luu, V. N.; 田崎 雄大; 宇田川 豊; 勝山 仁哉

Annals of Nuclear Energy, 231, p.112177_1 - 112177_16, 2026/06

https://doi.org/10.1016/j.anucene.2026.112177

Advanced technology fuels (ATF) with improved oxidation resistance are under development to enhance the safety of light water reactors. Cr-coated Zr alloy cladding, a promising near-term ATF, exhibits excellent oxidation resistance below the Cr-Zr eutectic temperature. However, its gradual loss of protective effect over time, even without mechanical damage, indicates the need to understand its degradation mechanisms. This article presents a phenomenological model describing degradation due to high-temperature oxidation, focusing on Zr ingress into the Cr coating and the formation of oxygen pathways that accelerate oxygen uptake into the Zr matrix. The model was validated against experimental data at 1200C and 1300C, reproducing key trends such as oxide growth, weight gain, and oxygen concentration profiles. Applying the same parameters to a different PVD-coated cladding test gave reasonable agreement at 1200C, while discrepancies at 1300C suggest Cr-Zr eutectic reactions from local temperature variations, highlighting the model's sensitivity near the eutectic point.

Analysis of fracture conditions of Cr-coated Zr alloy claddings under LOCA conditions calculated using FEMAXI fuel performance code

Luu, V. N.; 谷口 良徳; 宇田川 豊; 田崎 雄大; 勝山 仁哉

Annals of Nuclear Energy, 230, p.112114_1 - 112114_14, 2026/06

https://doi.org/10.1016/j.anucene.2026.112114

Fracture behavior of chromium (Cr) coated cladding under loss of coolant accident (LOCA) conditions was investigated utilizing the FEMAXI fuel performance code. Cr coating degradation models were introduced to FEMAXI to calculate oxygen diffusion behavior within the cladding tube. The FEMAXI code reasonably simulated the observed evolution of cladding metallic and oxide layers under the simulated LOCA conditions, accounting for factors such as wall thinning due to cladding high temperature creep, Cr layer thinning by CrO formation and Cr/Zr interdiffusion, weight increase by oxygen absorption, associated oxide growth, and increased oxygen concentration in -Zr phase. According to sensitivity analyses of the cladding oxygen concentration, where the effects of wall thickness change and eutectic reactions were taken into account, the fracture condition of the Cr-coated cladding samples can be reasonably modelled by the fracture criteria based on the remaining -Zr thickness with an oxygen concentration of 0.9 wt%.

A Method for estimating light quenching in inorganic scintillator detectors for radioactive ion beam experiments

Kreinder, B.; Cox, I.*; Grzywacz, R.*; 西尾 勝久; 他24名*

Nuclear Instruments and Methods in Physics Research A, 1085, p.171298_1 - 171298_7, 2026/05

https://doi.org/10.1016/j.nima.2026.171298

In recent experiments, inorganic scintillators have been used to study the decays of exotic nuclei, providing an alternative to silicon detectors and enabling measurements that were previously impossible. However, proper use of these materials requires us to understand and quantify the scintillation process, specifically in response to very heavy nuclei. In this work, we show a simplified method based on the models of Birks (1951) and Meyer and Murray (1962) to parametrize the light output of inorganic scintillators in response to beams of energetic heavy ions over a broad range of energies. We test the accuracy of our parametrization approach by calculating light output and quenching factors for various ions and comparing them with experimental data from Lutetium Yttrium Orthosilicate (LYSO:Ce), a common inorganic scintillator. The Meyer-Murray model suggests that, for sufficiently heavy ions at high energies, the majority of the light output is associated with the creation of delta electrons, which are induced by the passage of the beam through the material. These delta electrons dramatically impact the response of detection systems when subject to ions with velocities typical of beams in modern fragmentation facilities. To illustrate this, we also present a qualitative estimate of the effects of delta rays on overall light output using the Birks-Meyer-Murray parametrization. The approach presented herein will serve as a basic framework for further, more rigorous studies of scintillator response to heavy ions. This work is a crucial first step in planning future experiments where energetic exotic nuclei are interacting with scintillator detectors.

Microstructural evolution and mechanical hardening of Cr-coated MDA cladding under high-dose Fe ion irradiation

Mohamad, A. B.; Chen, J.*; 井岡 郁夫*; 鈴木 恵理子; 近藤 啓悦; 阿部 陽介; 山下 真一郎; 大久保 成彰; 根本 義之; 岡田 裕史*; et al.

Journal of Nuclear Materials, 625, p.156513_1 - 156513_9, 2026/04

https://doi.org/10.1016/j.jnucmat.2026.156513

Ion irradiation was carried out on Cr coating Zry cladding to investigate their microstructure evolution and mechanical properties. The sample was irradiated at reactor normal operation conditions. Microstructural observation and mechanical testing of non-irradiated samples and irradiated samples were performed to understand irradiation damage to the Cr-coated Zry cladding. Results of High Resolution Transmission Electron Microscopy and chemical analysis revealed Fe enrichment at the Cr coating and Zr substrate interface of irradiated samples due to irradiation enhanced diffusion or irradiation induced mixing. Irradiation led to the formation of Fe enrichment at the Cr Zr interface approximately 15nm. Moreover, hardening of the Cr coating and Zr substrate regions was observed in the irradiated sample.

HTTR(高温工学試験研究炉)の試験・運転と技術開発(2024年度)

高温工学試験研究炉部

JAEA-Review 2025-053, 86 Pages, 2026/02

JAEA-Review-2025-053.pdf:3.06MB

本報告書は、2024年度のHTTR(高温工学試験研究炉)の運転・保守管理状況、HTTRを用いた研究開発等についてまとめたものである。HTTRは熱出力30MW、原子炉出口冷却材温度950Cの我が国初の高温ガス炉の試験研究炉である。高温ガス炉は固有安全性に優れ、発電のみならず水素製造等の多様な産業利用が可能な原子炉として、将来の脱炭素社会に対応した次世代原子炉の候補として挙げられている。HTTRは2004年に熱出力30MWにおける原子炉出口冷却材温度950Cを到達して以来、安全性実証試験、長期連続運転等の高温ガス炉の研究開発に関する各種実証試験を重ね、長年に及ぶ高温ガス炉の運転・保守に係る経験を有している。2024年度は、HTTRに接続を計画している熱利用施設(水素製造施設)での設備機器異常による熱負荷変動を模擬した熱負荷変動試験と高温ガス炉の1次冷却設備二重管破断事故を想定し、配管内に沈着している放射性ヨウ素量を把握するための放射性ヨウ素定量評価試験を実施した。また、高温ガス炉による水素製造技術実証のため、原子力規制委員会に対しHTTRに水素製造施設を接続するための原子炉設置変更許可申請を実施した。

A Novel kinetic model for dissolution and precipitation of oxide on stainless-steel surface in stagnant liquid sodium

河口 宗道*; 池田 明日香; 斉藤 淳一

Annals of Nuclear Energy, 226, p.111880_1 - 111880_9, 2026/02

https://doi.org/10.1016/j.anucene.2025.111880

This study performed sodium experiments and developed a new kinetic model to investigate the oxide dissolution and precipitation behavior on the stainless-steel (SS) surface in stagnant liquid sodium. The experiment revealed that the oxygen of NaFeO on the SS surface was dissolved into the liquid sodium with v 9.3 10 wt.ratio/h in less than 20 h, and the oxide precipitation occurred on the SS surface with v 1.4 10 wt.ratio/h after the dissolution. Furthermore, the phase-field (PF) calculation code was developed to investigate the dependence of six parameters (T, c, , D , k, and t) of the oxide precipitation velocity in the liquid sodium. As a result, the precipitation velocity increased linearly as the oxygen concentration (c) and the oxygen diffusion coefficient (D) in liquid sodium increased. In contrast, its velocity decreased exponentially as the sodium temperature (T) and the interfacial energy of oxide () increased. The quasi-partial coefficient (k) and the time step (t) did not affect the calculation results at all. In these sensitivity analyses, the oxide precipitation velocity obtained by the PF calculation shows consistency with the laboratory-scale experimental findings of Latge et al.

Ambient dose rate variation in the Fukushima region visualized using explainable AI techniques

吉田 竜*; 操上 広志; 長尾 郁弥; 高橋 成雄*; 眞田 幸尚

Journal of Environmental Radioactivity, 293, p.107900_1 - 10790_13, 2026/02

https://doi.org/10.1016/j.jenvrad.2026.107900

Following the Fukushima Daiichi Nuclear Power Station accident in 2011, ambient dose rates in the surrounding region have gradually declined due to radioactive decay and decontamination efforts. However, spatial variations in dose rate reduction remain insufficiently understood, particularly in forested areas where contamination persists. This study investigates long-term trends in ambient dose rate changes using explainable AI techniques. A 12-year integrated dose rate map, combining fixed-point, walk, carborne, and airborne survey data, was used to analyze temporal and spatial patterns. We developed a predictive model using Light Gradient Boosting Machine (LightGBM) to estimate dose rate reduction ratios based on geographic and environmental features. SHapley Additive Explanations (SHAP) were applied to quantify the contribution of each variable and enhance model interpretability. Our findings revealed that land use significantly influences dose rate reduction, with urban and agricultural areas showing faster declines due to infrastructure and human activity including decontamination works, while forests exhibit slower reductions. Notably, topographical features such as elevation and slope affect dose rate trends in undisturbed forests, with valleys and depressions showing stagnation. This study provided the first visual validation of area-wide decontamination effects and demonstrates the utility of explainable AI in environmental radiation analysis. The proposed approach offers a robust framework for geospatial interpretation and supports future policymaking for regional recovery and forest utilization.

Feasibility study of machine learning-based discrimination of , and particles from grayscale radiation images

Laffolley, H.; 坪田 陽一; 辻 智也; 本田 文弥

Nuclear Instruments and Methods in Physics Research A, 1082(Part 2), p.171029_1 - 171029_11, 2026/02

https://doi.org/10.1016/j.nima.2025.171029

日本原子力研究開発機構(JAEA)は福島第一原子力発電所の廃炉作業において、多種多様な放射性試料を分析している。本研究は、多種多様な試料の特性評価プロセスの簡素化と省力化に資する多目的な分析ツールを開発することである。ハイブリッド半導体ピクセル放射線検出器であるMiniPIX TPX Standard検出器を基に、分析装置の開発を開始した。この検出器は、電離放射線の相互作用に基づくグレースケール画像を得ることができ、ピクセルの輝度はエネルギーに対応している。最終的な目標は、、、放射線を区別し、高度に汚染されたサンプルに対して簡便な線スペクトロメトリを含む2次元放射能マップを高速に生成する装置を構築することである。放射線と半導体との相互作用によって生成されたクラスタの形状は、その線種に応じた特徴的な形状となる。放射線画像のクラスタに対し、9つの特徴量に基づき、8つの教師あり機械学習モデルで学習と比較を行った。訓練データセットとしては線(Am)、線(Sr)、線(Co及びCs)に対応する画像を用いた。最良のモデルは約80%の精度で粒子を識別でき、低エネルギー線のみの露光の場合には96%の精度に達し、1画像フレームあたり数マイクロ秒の処理時間で動作する。粒子の識別は100%の精度であった。

Separation of Rh(III) and direct electrodeposition in phosphonium-based ionic liquids with electrochemical and spectroscopic analyses for extracted Rh(III) complex

徳満 駿*; 松宮 正彦*; 佐々木 祐二

Separation and Purification Technology, 382(Part 2), p.135631_1 - 135631_9, 2026/02

https://doi.org/10.1016/j.seppur.2025.135631

Solvent extraction (SX) of Rh(III) and direct electrodeposition (ED) of Rh metal were carried out in five cycles using phosphonium-based ionic liquids (ILs). The comparatively high extraction performance (70.1%-86.2%) of Rh(III) was stably retained in each SX process. In the subsequent ED process, the electrodeposits were recovered on the cathode and the reasonable current efficiencies (74.9%-85.6%) were achieved in the IL system. The X-ray photoelectron spectroscopy revealed that the electrodeposits obtained during ED process were found to be in the metallic state.

簡易非破壊測定に向けた革新的なn・シンチレーション検出システムの開発(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; 東北大学*

JAEA-Review 2025-046, 70 Pages, 2026/01

JAEA-Review-2025-046.pdf:5.46MB

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(1F)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5年度に採択された研究課題のうち、「簡易非破壊測定に向けた革新的なn・シンチレーション検出システムの開発」の令和5年度の研究成果について取りまとめたものである。令和5年度に1Fでは、原子炉格納容器(PCV)からの燃料デブリの取り出しが予定され、さらに、将来的には段階的な取り出し規模の拡大が検討されている。本研究では、標的試料取り出し時のスクリーニングならびに連続監視に資する、革新的なシンチレーション放射線検出システムを開発する。また、1Fをはじめとした原子力施設廃止措置の炉内調査に資する遠隔測定システムを実用化する。より具体的には、(1)革新的な中性子・線核種弁別シンチレータの研究(東北大学)、(2)センサーならびに信号処理システムの小型化(東京大学)、(3)多様な放射線場構築と特性評価(産業技術総合研究所)、(4)簡易非破壊測定システムの開発とホットセル内実証試験(原子力機構)の各要素技術に対し、垂直統合的に研究を展開することでPCV内や各受け入れセル内において、10Gy/hを超える環境下で線、中性子線を弁別し、それぞれの線量率と核種同定を同時に行う検出器の開発に向け、令和5年度に計画した各研究項目に関する研究開発を実施した。