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Jeong, S. G.*; Kwon, J.*; Kim, E. S.*; Prasad, K.*; Harjo, S.; Gong, W.; 川崎 卓郎; Estrin, Y.*; Bouaziz, O.*; Hong, S. I.*; et al.
Materials Science & Engineering A, 942, p.148712_1 - 148712_11, 2025/10
The cellular structure plays a key role in determining the mechanical properties of metal additive manufacturing (MAM) components. This study presents in situ neutron diffraction and dislocation density-based modeling for a CoCrFeMnNi high-entropy alloy (HEA) made via directed energy deposition (DED). A constitutive model based on the Kocks-Mecking-Estrin framework was used to represent the cellular structure. Parametric analysis showed lower dislocation accumulation and annihilation rates in the as-built sample (with cellular structure) than in the heat-treated one. These differences are linked to dislocation forest networks and local stacking fault energy variations. Dislocation density across cell interiors and walls was also compared with deformation-induced dislocation cells.
高梨 美咲*; 日高 僚太*; 大久保 亘太*; 増村 拓朗*; 土山 聡宏*; 諸岡 聡; 前田 拓也*; 中村 修一*; 植森 龍治*
ISIJ International, 65(9), p.1384 - 1393, 2025/08
This study investigates the strengthening mechanism of ausforming in martensitic steels, focusing on the role of dislocation inheritance from austenite. By analyzing Fe-5%Mn-C alloys, the researchers quantified dislocation densities before and after ausforming and examined how carbon content affects hardening. Results show that both hardness and dislocation density of ausformed martensite increase with greater deformation in austenite and higher carbon content. The findings support that ausforming strengthens martensite through dislocation accumulation, consistent with the Bailey-Hirsch relationship. 
neutron diffraction revealed that dislocation inheritance occurs only in steels with sufficient carbon, while additional dislocations are introduced during martensitic transformation.
竹田 武司
JAEA-Data/Code 2025-005, 106 Pages, 2025/06
JAEA-Data-Code-2025-005.pdf:2.93MB
JAEAでは、加圧水型軽水炉(PWR)解析のためのRELAP5/MOD3.3コードの入力データを、主に大型非定常実験装置(LSTF)の参照4ループPWRである敦賀発電所2号機の設計情報を基に作成してきた。PWR解析に関する代表的なOECD/NEAの活動として、BEMUSEプログラムの枠組みにおける低温側配管大破断冷却材喪失事故(LBLOCA)の計算が挙げられる。また、わが国の新規制基準に係るPWRの炉心損傷防止対策の有効性評価事象には、低温側配管LBLOCA時の非常用炉心冷却系(ECCS)の再循環機能喪失事象が含まれる。本検討において、PWRの安全設計上想定すべき設計基準事故の一つであるLBLOCAを解析するための入力データを整備した。本報告書では、PWRLBLOCA解析の入力データの主な特徴を示す。PWRの原子炉容器、加圧器(PZR)、高温側配管、蒸気発生器(SG)、SG二次系、クロスオーバーレグ、低温側配管、ECCSなどをモデル化し、参照4ループPWRを2ループで模擬した。その際、PZRは3ループ分を模擬するループAに接続し、破断口は1ループ分を模擬するループBに設置した。PWRのコンポーネントのノード分割は、LSTFのコンポーネントのノード分割を参照した。また、PWRLBLOCA解析の主な入力データに対して、解釈を加えるとともに、設定根拠などの付加情報を提供した。さらに、整備した入力データを用いて、ECCS再循環機能喪失事象を対象とした過渡解析を実施した。RELAP5/MOD3.3コードによる既往研究の計算と比較することにより、過渡解析は概ね妥当であることを確認した。加えて、RELAP5/MOD3.3コードを用いて感度解析を実施し、破断口の流出係数や代替再循環注水流量が燃料棒被覆管表面温度に及ぼす影響を明らかにした。本報告書では、設定した条件の範囲内での感度解析結果について示し、ECCS再循環機能喪失事象に対する既往研究の計算内容の一部を補完する。
高梨 美咲*; 日高 僚太*; 大久保 亘太*; 増村 拓朗*; 土山 聡宏*; 諸岡 聡; 前田 拓也*; 中村 修一*; 植森 龍治*
鉄と鋼, 111(9), p.503 - 513, 2025/06
The strengthening mechanism of ausforming in martensitic steels is believed to be due to the inheritance of dislocations in austenite by the subsequently transformed martensite. However, no studies to date have quantified the dislocation density before and after ausforming. In this study, the dislocation densities of Fe-5%Mn-C alloys were analyzed, and the relationship between hardening by ausforming and dislocation accumulation, as well as the effect of carbon on this relationship, were investigated. The hardness of ausformed martensite increased with the ausforming reduction in austenite, and the strengthening effect of ausforming increased with the addition of carbon. Similarly, the dislocation density of ausformed martensite increased with the ausforming reduction in austenite, and the dislocation accumulation by ausforming increased with the addition of carbon. Because the hardness of the ausformed martensite follows the Bailey-Hirsch relationship, the strengthening mechanism owing to ausforming could be explained by dislocation strengthening. To understand the dislocation accumulation process during ausforming, the dislocation density of austenite immediately after ausforming was measured by in-situ heating neutron diffraction. Consequently, the dislocation density of the ausformed austenite was not dependent on the carbon content, indicating that dislocations are not inherited in carbon-free steels. By contrast, in steels with sufficient carbon content, not only are dislocations inherited but additional dislocations are introduced during martensitic transformation.
Naeem, M.*; Ma, Y.*; Tian, J.*; Kong, H.*; Romero-Resendiz, L.*; Fan, Z.*; Jiang, F.*; Gong, W.; Harjo, S.; Wu, Z.*; et al.
Materials Science & Engineering A, 924, p.147819_1 - 147819_10, 2025/02
被引用回数：1 パーセンタイル：63.96(Nanoscience & Nanotechnology)Face-centered cubic (fcc) medium-/high-entropy alloys (M/HEAs) typically enhance strength and ductility at cryogenic temperatures via stacking faults, twinning, or martensitic transformation. However, in-situ neutron diffraction on VCoNi MEA at 15 K reveals that strain hardening is driven solely by rapid dislocation accumulation, without these mechanisms. This results in increased yield strength, strain hardening, and fracture strain. The behavior, explained by the Orowan equation, challenges conventional views on cryogenic strengthening in fcc M/HEAs and highlights the role of dislocation-mediated plasticity at low temperatures.
佐藤 聡; 日引 俊*; 池田 遼; 柴本 泰照
Progress in Nuclear Energy, 180, p.105593_1 - 105593_11, 2025/02
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)加圧水型原子炉(PWR)の冷却材喪失事故では、ダウンカマーに流入するコールドレグに注入された緊急炉心冷却(ECC)水の流れにより、原子炉圧力容器(RPV)内壁に加圧熱衝撃(PTS)が発生するリスクがある。PTSは、ECC水によるダウンカマー壁の急冷によって発生し、ECC水の温度、壁面へのジェットの衝突位置と速度、壁面上の液膜の速度、液膜の厚さ、下降流の広がりなどに強く影響される。したがって、コールドレグからダウンカマーに流出するECC水の流れは、PTS事象に強く影響する可能性がある。この流動現象を理解するために、円管からの自由流出に関する研究をレビューした。流動条件の分類、流動条件間の遷移条件、端部深さ比、円管内の流れの自由表面形状、管から流出するナッペの形状に関する実験結果は、ほぼ一致した形で得られている。これに対し、コールドレグからダウンカマーへの流れを考慮する場合、自由空間ではなく狭い隙間への流れ、円管出口の角の丸みの存在、炉心からコールドレグへ流れる蒸気流の影響など、特殊な状況での流れ場を扱う必要がある。しかし、これらの要因を考慮した先行研究は少ないため、今後蓄積すべき知見としてまとめた。
竹田 武司
JAEA-Data/Code 2024-014, 76 Pages, 2024/12
JAEA-Data-Code-2024-014.pdf:4.0MB
ROSA-V計画において、大型非定常実験装置(LSTF)を用いた実験(実験番号:SB-PV-03)が2002年11月19日に行われた。ROSA/LSTFSB-PV-03実験では、加圧水型原子炉(PWR)の0.2%圧力容器底部小破断冷却材喪失事故を模擬した。このとき、非常用炉心冷却系(ECCS)である高圧注入系の全故障とともに、蓄圧注入(ACC)タンクから一次系への非凝縮性ガス(窒素ガス)の流入を仮定した。また、アクシデントマネジメント(AM)策として両蒸気発生器(SG)二次側減圧を安全注入設備信号発信後10分に一次系減圧率55K/hを目標として開始し、その後継続した。さらに、AM策から少し遅れて両SG二次側への30分間の補助給水を開始した。ACCタンクから一次系への窒素ガスの流入開始まで、AM策は一次系減圧に対して有効であった。ACC系から両低温側配管への間欠的な冷却材注入により、炉心水位は振動しながら回復した。このため、炉心水位は小さな低下にとどまった。窒素ガスの流入後、一次系とSG二次側の圧力差が大きくなった。窒素ガス流入下におけるSG伝熱管でのリフラックス凝縮時に、ボイルオフによる炉心露出が生じた。模擬燃料棒の被覆管表面最高温度がLSTFの炉心保護のために予め決定した値(908K)を超えたとき、炉心出力は自動的に低下した。炉心出力の自動低下後、ECCSである低圧注入(LPI)系から両低温側配管への冷却材注入により、全炉心はクエンチした。LPI系の作動を通じた継続的な炉心冷却を確認後、実験を終了した。本報告書は、ROSA/LSTFSB-PV-03実験の手順、条件および実験で観察された主な結果をまとめたものである。
高松 邦吉; 舩谷 俊平*
Proceedings of 13th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS13) (Internet), 11 Pages, 2024/11
本研究は、外的ハザードに対する安全性向上に向けて、水や空気等の流体の駆動に期待するのではなく、事故時の崩壊熱及び残留熱を受動的に冷却可能な、放射冷却を利用した新たな冷却システム(炉容器冷却システム)の開発を目的とする。本発表では、提案する炉容器冷却システムを原子炉建家と一体化した構造概念を提示するとともに、これまでの実験及び解析検討結果に基づく性能評価結果を報告する。
neutron diffraction study to elucidate hydrogen effect on the deformation mechanism in Type 310S austenitic stainless steel伊東 達矢; 小川 祐平*; Gong, W.; Mao, W.*; 川崎 卓郎; 岡田 和歩*; 柴田 曉伸*; Harjo, S.
Proceedings of the 7th International Symposium on Steel Science (ISSS 2024), p.237 - 240, 2024/11
Hydrogen embrittlement has long been an obstacle to the development of safe infrastructure. However, in contrast to hydrogen's embrittling effect, recent research has revealed that the addition of hydrogen improves both the strength and uniform elongation of AISI Type 310S austenitic stainless steel. A detailed understanding of how hydrogen affects the deformation mechanism of this steel could pave the way for the development of more advanced materials with superior properties. In the present study, 
neutron diffraction experiments were conducted on Type 310S steel with and without hydrogen-charged to investigate the effect of hydrogen on the deformation mechanism. In addition to the effect of solid-solution strengthening by hydrogen, the q-value, a parameter representing the proportion of edge and screw dislocations in the accumulated dislocations, was quantitatively evaluated using CMWP analysis on neutron diffraction patterns. The comparison of q-values between the hydrogen-charged and non-charged samples reveals that hydrogen has minimal effect on dislocation character in Type 310S steel.
田崎 雄大; 成川 隆文; 宇田川 豊
Journal of Nuclear Science and Technology, 61(10), p.1349 - 1359, 2024/10
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)This study developed a probabilistic determination model with respect to cladding high-temperature burst conditions based on the Bayesian statistical method to reasonably evaluate fuel behaviors under loss-of-coolant accident conditions, including fuel fragmentation, relocation, and dispersal. The candidate models were based on the widely accepted empirical model established based on nonirradiated fuel cladding data. Explanatory variables were added to improve the applicability of these models with respect to irradiated materials and generalization performance. The posterior predictive distribution of each candidate model was evaluated using Bayesian estimation comprising 238 sets of high-temperature burst test data. The generalization performance was evaluated using information criteria. The results of model evaluation showed improved predictive performance by considering the effect of hydrogen content. A comparison with burnup as an alternative explanatory variable confirmed that hydrogen content was the better parameter and other burnup-associated effects, such as irradiation hardening of the metal matrix and oxide growth (reduction of the metal matrix), were less dominant under burst conditions.
曽我部 丞司; 石田 真也; 田上 浩孝; 岡野 靖; 神山 健司; 小野田 雄一; 松場 賢一; 山野 秀将; 久保 重信; 久保田 龍三朗*; et al.
Proceedings of International Conference on Nuclear Fuel Cycle (GLOBAL2024) (Internet), 4 Pages, 2024/10
日仏協力の枠組みにおいて、タンク型ナトリウム冷却高速を対象とした過酷事故の評価手法を定義し、解析評価を実施した。
Li, F.; 成川 隆文; 宇田川 豊
Journal of Nuclear Science and Technology, 61(8), p.1036 - 1047, 2024/08
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)The seismic resistance of fuel cladding during the long-term core cooling after loss-of-coolant accidents (LOCAs) was investigated by performing cyclic four-point bending tests (4PBTs) of up to 1000 cycles with fresh fuel cladding samples that experienced integral thermal shock test, simulating LOCA conditions, including ballooning, rupture, oxidation, and quench. 4PBTs were performed on the samples that survived the quenching process. The results showed that up to 1000 cycles and 5.8 Nm of cyclic loading moment, there was no apparent effect on the bending fracture limit of the fuel cladding under the 4PBT. The scatter of the bending fracture limit for a given equivalent cladding reacted (ECR) evaluated by the Baker-Just oxidation rate equation (BJ-ECR) is attributed to two primary factors: first, the difference between the prescribed and the actual oxidation behavior, confirmed by comparing the BJ-ECR and the ECR evaluated based on metallographic observation (M-ECR), and second, the variated shape of the rupture-opening area after the integral thermal shock test. The strength of the alpha phase-dominant zone near the rupture opening seems to contribute to the bending fracture limit.
CNguyen, B. V. C.*; 村上 健太*; Chena, L.*; Phongsakorn, P. T.*; Chen, X.*; 橋本 貴司; Hwang, T.*; 古澤 彰憲; 鈴木 達也*
Nuclear Materials and Energy (Internet), 39, p.101639_1 - 101639_9, 2024/06
被引用回数：1 パーセンタイル：82.28(Nuclear Science & Technology)In reactor pressure vessel materials, the formation of Mn- and Ni-rich nanoclusters is a major cause of neutron irradiation embrittlement. The segregation of these solute atoms into dislocation loops has attracted attention as a mechanism to accelerate solute clustering. In this study, the behaviors of solute Mn and Ni atoms in Fe-0.6wt.%Ni, Fe-1.4wt.%Mn, and Fe-1.4wt.%Mn-0.6wt.%Ni alloys irradiated at 400 C up to 3 dpa were analyzed using three-dimensional atom probe tomography. Solute atom clusters were observed in all materials, and their shapes were spherical, flat, and torus in FeNi, FeMn, and FeMnNi, respectively. In ternary alloy FeMnNi, Mn and Ni atoms were concentrated in the sample in the form of arcs, and the orientation of the plane containing the arcs was estimated by comparing field desorption images. The size, number density, and orientation of this structure were found to be in good agreement with those of both types of dislocation loops, namely, b = 1/2 
111
and b = 100, identified in a previous study using the same material. The positions of Ni and Mn enrichment did not fully overlap. Ni atoms tended to be concentrated more in the inner part of the loop than the Mn atoms. Mn atoms were enriched only in the vicinity of the dislocation loops, whereas Ni atoms showed a higher concentration inside the dislocation loops than in the bulk.
F勝又 哲裕*; 鈴木 涼*; 佐藤 直人*; 小田 良哉*; 本山 慎吾*; 鈴木 俊平*; 中島 護*; 稲熊 宜之*; 森 大輔*; 相見 晃久*; et al.
Chemistry of Materials, 36(8), p.3697 - 3704, 2024/04
被引用回数：1 パーセンタイル：15.31(Chemistry, Physical)ペロブスカイト型酸窒化物のBaFeOFを高圧合成によって作製した。得られた物質はSHGシグナルが観測されたことから自発分極の存在を示唆していたため、分極発現機構を放射光高エネルギーX線回折で調べた。得られた2体相関分布関数をフィットした結果、方位の異なる局所的な分極発現機構を見出した。BaFeOFは磁性材料でもあるため、磁気ドメインと強誘電ドメインが共存していると考えられる。
高松 邦吉; 舩谷 俊平*
Nuclear Engineering and Technology, 56(3), p.832 - 845, 2024/03
被引用回数：1 パーセンタイル：35.03(Nuclear Science & Technology)受動的安全性を持つRCCSは、大気を冷却材として使用するため、冷却材を喪失することはないが、大気の擾乱の影響を受けやすいという欠点がある。そのため、大気放射を利用したRCCSと、大気自然循環を利用したRCCSを実用化するためには、想定される自然災害や事故状態を含むあらゆる状況下で、原子炉からの発熱を常に除去できるのかについて安全評価を実施する必要がある。そこで本研究では、2種類の受動的RCCSについて、熱除去のための受動的安全性の余裕(裕度)について同一条件で比較した。その結果、提案した大気輻射を利用したRCCSは、外気(大気)の擾乱に対して原子炉圧力容器(RPV)の温度を安定的に維持できる利点を明らかにすることができた。さらに、RPV表面から放出される廃熱をすべて利用できる方法も提案した。
成川 隆文; 宇田川 豊
Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 10 Pages, 2024/03
Information criteria such as a widely applicable information criterion (WAIC) and a widely applicable Bayesian information criterion (WBIC) enable the selection of models with high predictive accuracy and data fit, yet these criteria come with inherent uncertainties as they are statistical measures. To evaluate the uncertainty in model selection based on these information criteria, we performed numerical experiments using the bootstrap method, which is a resampling technique, on models for estimating the fracture probability of fuel cladding tubes during loss-of-coolant accidents (LOCAs). By calculating WAIC and WBIC for each of 10,000 bootstrap samples, we evaluated the dependency of model selection on these samples. Our key findings reveal that: (1) Sample-derived variation in information criteria was significantly greater than variability between models, underscoring the importance of assessing uncertainty from samples. (2) The Log-probit model, developed in our previous study, was selected as the optimal model for its superior predictive performance and data fit, despite the inherent uncertainties associated with WAIC and WBIC. (3) The presence of outliers at the fracture/non-fracture boundary of fuel cladding tubes may negatively impact the information criteria, suggesting the need for careful consideration when including such data in model parameter estimation.
小山 元道*; 山下 享介*; 諸岡 聡; 澤口 孝宏*; Yang, Z.*; 北條 智彦*; 川崎 卓郎; Harjo, S.
鉄と鋼, 110(3), p.197 - 204, 2024/02
被引用回数：1 パーセンタイル：20.31(Metallurgy & Metallurgical Engineering)The local plasticity and associated microstructure evolution in Fe-5Mn-0.1C medium-Mn steel (wt.%) were investigated in this study. Specifically, the micro-deformation mechanism during L
ders banding was characterized based on multi-scale electron backscatter diffraction measurements and electron channeling contrast imaging. Similar to other medium-Mn steels, the Fe-5Mn-0.1C steel showed discontinuous macroscopic deformation, preferential plastic deformation in austenite, and deformation-induced martensitic transformation during Lders deformation. Hexagonal close-packed martensite was also observed as an intermediate phase. Furthermore, an in-situ neutron diffraction experiment revealed that the pre-existing body- centered cubic phase, which was mainly ferrite, was a minor deformation path, although ferrite was the major constituent phase.
小山 元道*; 山下 享介*; 諸岡 聡; Yang, Z.*; Varanasi, R. S.*; 北條 智彦*; 川崎 卓郎; Harjo, S.
鉄と鋼, 110(3), p.205 - 216, 2024/02
被引用回数：0 パーセンタイル：0.00(Metallurgy & Metallurgical Engineering) deformation experiments with cold-rolled and intercritically annealed Fe-5Mn-0.1C steel were carried out at ambient temperature to characterize the deformation heterogeneity during Lders band propagation. Deformation band formation, which is a precursor phenomenon of Lders band propagation, occurred even in the macroscopically elastic deformation stage. The deformation bands in the Lders front grew from both the side edges to the center of the specimen. After macroscopic yielding, the thin deformation bands grew via band branching, thickening, multiple band initiation, and their coalescence, the behavior of which was heterogeneous. Thick deformation bands formed irregularly in front of the region where the thin deformation bands were densified. The thin deformation bands were not further densified when the spacing of the bands was below 
10 
m. Instead, the regions between the deformation bands showed a homogeneous plasticity evolution. The growth of the thin deformation bands was discontinuous, which may be due to the presence of ferrite groups in the propagation path of the deformation bands. Based on these observations, a model for discontinuous Lders band propagation has been proposed.
Kim, G.*; Cho, S.-M.*; Im, S.*; Suh, H.*; 諸岡 聡; 菖蒲 敬久; 兼松 学*; 町田 晃彦*; Bae, S.*
Construction and Building Materials, 411, p.134529_1 - 134529_18, 2024/01
被引用回数：12 パーセンタイル：72.15(Construction & Building Technology)This study explores the influence of the interatomic structure of sodium aluminosilicate hydrate (N-A-S-H) with varying silica contents on the mechanical properties of metakaolin-based geopolymer. Geopolymer pastes comprising Si/Al ratios between 2.0 and 3.0 were synthesized. A larger number of Si-O-Si linkages compared to Si-O-Al linkages and a higher atomic number density were found in the geopolymers with higher silica contents, which enhanced the compressive strength of the geopolymer pastes up to the optimal Si/Al ratio of 2.5. The paste with a Si/Al = 2.5 exhibited a greater portion of Q
(1Al and 2Al) and denser morphology compared to the other geopolymer pastes. Furthermore, in-situ high-energy synchrotron X-ray scattering experiments were conducted to assess the elastic modulus of the aluminosilicate structure at a local atomic scale. The modulus value in real space decreases with increasing silica contents up to Si/Al = 2.5 and increases with the presence of excessive unreacted silica fume. The modulus value in reciprocal space for the axial and lateral directions both presented a positive value at the geopolymer comprising a Si/Al ratio higher than 2.5, indicating that the load-bearing property of N-A-S-H changed at higher Si/Al ratios. Moreover, the smallest difference between the strains along the axial and lateral directions was detected for the geopolymer with Si/Al = 2.5 in both the real and reciprocal space, owing to the most interconnected and flexible nanostructure, which led to the highest mechanical strength.
成川 隆文; 近藤 啓悦; 藤村 由希; 垣内 一雄; 宇田川 豊; 根本 義之
Journal of Nuclear Materials, 587, p.154736_1 - 154736_8, 2023/12
被引用回数：3 パーセンタイル：51.01(Materials Science, Multidisciplinary)To evaluate the oxidation and embrittlement behavior of an oxide-dispersion-strengthened FeCrAl (FeCrAl-ODS) cladding tube under loss-of-coolant accident (LOCA) conditions, we conducted isothermal oxidation and ring-compression tests on unirradiated, stress-relieved FeCrAl-ODS cladding tube specimens. Further, we discussed the loss of coolable geometry of the reactor core loaded with the FeCrAl-ODS cladding tubes under LOCA conditions, using data from the ring-compression tests in this study and the integral thermal shock tests from our previous study. The results reveal that oxidation kinetics of the FeCrAl-ODS cladding tube at 1523 K is four orders of magnitude lower than that of a conventional Zircaloy cladding tube, which highlights the exceptional oxidation resistance of the FeCrAl-ODS cladding tube. The breakaway oxidation of the FeCrAl-ODS cladding tube was observed at 1623 K for durations equal to or exceeding 6 h, and melting was observed at 1723 K. The ring-compression and the integral thermal shock tests indicate that, depending on the oxidation time, the ductile to brittle transition threshold - as determined by the ring-compression test - exists between 1623 K and 1723 K. Meanwhile, the fracture threshold - established through the integral thermal shock test - falls between 1573 K and 1673 K. Therefore, taking a conservative approach based on available data, the fracture and non-fracture results from the integral thermal shock tests can define the lower and upper boundaries of the threshold for the loss of coolable geometry of the reactor core during a LOCA.
