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Journal Articles

Unveiling the effects of Mn, Cr, Al, and Si on the low-temperature tempering behaviors of high-carbon martensite

Zhang, Y.*; Marusawa, Kenji*; Kudo, Kohei*; Morooka, Satoshi; Gong, W.; Harjo, S.; Miyamoto, Goro*; Furuhara, Tadashi*

Journal of Materials Science & Technology, 275, p.250 - 259, 2026/12

Journal Articles

Directional fast neutron detectors for neutron source surveys over large areas

Hironaka, Kota; Koizumi, Mitsuo; Mochimaru, Takanori*; Takahashi, Tone; Yamanishi, Hirokuni*; Wakabayashi, Genichiro*

Nuclear Instruments and Methods in Physics Research A, 1090, p.171675_1 - 171675_7, 2026/10

Journal Articles

Probabilistic fracture mechanics benchmarking study of PASCAL-SP code with xLPR code regarding primary water stress corrosion cracking

Mano, Akihiro; Yamaguchi, Yoshihito; Katsuyama, Jinya

International Journal of Pressure Vessels and Piping, 222, p.105792_1 - 105792_11, 2026/08

 Times Cited Count:0 Percentile:0.00

A probabilistic fracture mechanics (PFM) analysis code, PASCAL-SP, has been developed by the Japan Atomic Energy Agency (JAEA) to evaluate the failure probability of piping within nuclear power plants while considering age-related degradations such as stress corrosion cracking and fatigue for both pressurized water reactor and boiling water reactor environments. To strengthen the confidence in the results of PASCAL-SP, a benchmarking study was performed with the PFM analysis code, xLPR, which was developed by the U.S.NRC in collaboration with EPRI. In this benchmarking study, deterministic and probabilistic analyses are performed using common analysis conditions. This paper presents the details of these conditions and comparisons of the results between the two aforementioned codes. Both codes were found to provide nearly the same results in both deterministic and probabilistic analyses for a dissimilar metal weld subjected to primary water stress corrosion cracking.

Journal Articles

Fundamental consideration of maximum allowable flaw lengths for limit load evaluation based on flat plates for the ASME Code Section XI

Negyesi, M.*; Hasegawa, Kunio

Journal of Pressure Vessel Technology, 148(4), p.044501_1 - 044501_4, 2026/08

Journal Articles

Real-time inversion of radioactive source distribution using air dose rate measurements via least absolute shrinkage and selection operator method

Shi, W.*; Machida, Masahiko; Okamoto, Koji*; Luo, X.*; Feng, W.*; Liu, X.*

Reliability Engineering & System Safety, 272, Part1, p.112538_1 - 112538_18, 2026/08

The reliability of emergency response in severe nuclear accidents critically depends on robust real-time monitoring of radioactive source distributions. However, this safety function is challenged by physical constraints that create monitoring blind spots and by the inadequacy of static methods in tracking dynamic releases. To enhance the reliability and robustness of source term estimation, this study proposes a dynamic reconstruction framework based on LASSO regression with temporal regularization. A sliding-window time-penalty mechanism is introduced, imposing $$L_2$$-norm constraints on inter-step source variations to ensure physical continuity. The contribution matrix and measurement vector are normalized to counteract biases from radiation shielding and time-varying intensities. Validation using a two-room model with internal shielding, with PHITS Monte Carlo simulation, demonstrates accurate reconstruction of dynamic sources from remote measurements. Temporal regularization enhances situational awareness by suppressing spatial aliasing: at sliding-window width $$T = 1$$ (no regularization), hotspot locations fluctuate significantly, with quantitative mean absolute error fluctuations at around $$5.4 times 10^{-3}$$, whereas $$T geq 2$$ yields improved spatial consistency and the fluctuation quantities decrease to the $$3.1 times 10^{-3}$$ range. Comparative analysis identifies $$T = 2$$ as optimal in balancing accuracy and computational cost. This work establishes a more reliable pathway for dynamic hazard assessment, enabling accurate localization and intensity tracking under challenging conditions. The proposed framework provides a decision-support tool enhancing the resilience and safety of emergency management in nuclear facilities.

Journal Articles

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

Abe, Takumi; Suzuki, Taiga*; Okamura, Tomohiro*; Nakase, Masahiko*

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

 Times Cited Count:0 Percentile:0.00

Journal Articles

Prediction of tumor control probability in prostate cancer radiotherapy using a biophysical model incorporating cancer stem cell and hypoxia

Saga, Ryo*; Iwamori, Kenta*; Matsuya, Yusuke; Hosokawa, Yoichiro*

Computers in Biology and Medicine, 211, p.111743_1 - 111743_10, 2026/07

This study developed a biophysical model that integrates the characteristics of cancer stem cells (CSCs), including the side population (SP), and the oxygen enhancement effect (OER) to more accurately predict radiotherapy outcomes in prostate cancer. SP and main population (MP) cells were isolated from the DU145 prostate cancer cell line, and DNA double-strand breaks and survival were evaluated under both normoxic and hypoxic conditions ($$<$$0.1% O$$_{2}$$). The obtained data were analyzed using the IMK model incorporating MP, SP, and oxygen concentration, and the predictions were compared with clinical tumor control probability (TCP) under various fractionation regimens (2, 3, and 7 Gy/Fx). As a result, the in vitro and clinical data were well reproduced by considering the MP/SP fraction, a population-independent OER, and the intratumoral hypoxic volume. Furthermore, the initial yield of DSBs was identified as a key determinant of radiosensitivity depending on cell characteristics and oxygen levels. The developed model is expected to contribute to the optimization of prostate cancer radiotherapy, including dose escalation to hypoxic tumor regions.

Journal Articles

Mechanistic insights into volatile ruthenium tetroxide formation during evaporation-to-dryness accidents of high-level liquid waste

Yoshida, Naoki; Amano, Yuki; Yoshida, Ryoichiro; Ono, Takuya; Tashiro, Shinsuke; Yamane, Yuichi

Journal of Hazardous Materials, 513, p.142332_1 - 142332_20, 2026/07

Volatile ruthenium tetroxide (RuO$$_{4}$$) formed during evaporation-to-dryness accidents (EDA) of high-level liquid waste (HLLW) combines high chemical toxicity with radiotoxicity from isotopes such as $$^{103}$$Ru and $$^{106}$$Ru, making it a primary hazard in nuclear-fuel reprocessing. This study experimentally elucidates the mechanisms governing RuO$$_{4}$$ formation while testing the validity of the pragmatic nitrosyl-ruthenium ([RuNO]) surrogate model, an experimental model that assumes Ru in HLLW exists as [RuNO], and evaluates gaseous Ru release using nitric acid solutions of [RuNO], commonly used in RuO$$_{4}$$ release assessments by comparing it with the behavior of simulated HLLW (s-HLLW). We systematically investigated potential pathways, including oxidation by liquid-phase nitric acid (HNO$$_{3}$$(l)), gas-phase nitric acid (HNO$$_{3}$$(g)), and oxygen (O2); thermal decomposition of [RuNO]; and matrix effects of coexisting nitrates. The results identify oxidation by activated HNO$$_{3}$$(l), oxidation by HNO$$_{3}$$(g) and thermal decomposition of [RuNO] as the principal routes to RuO$$_{4}$$, with HNO$$_{3}$$(g) playing a far more significant role than previously recognized. Crucially, the RuO$$_{4}$$ release profile from s-HLLW differed markedly from that predicted by the [RuNO] surrogate model, demonstrating that this model fails to capture the complex matrix effects and time-dependent chemical changes of Ru species inherent to real HLLW. These findings have significant implications for improving the accuracy of hazard assessments related to RuO$$_{4}$$ release during HLLW EDAs, particularly by highlighting the limitations of commonly used [RuNO] surrogate models.

Journal Articles

Trade-off between adsorption capacity and binding strength regulates carbon stabilization in mineral-associated organic matter

Sun, R.; Abe, Yukiko; Atarashi-Andoh, Mariko; Koarashi, Jun

Soil Biology & Biochemistry, 218, p.110150_1 - 110150_12, 2026/07

The role of minerals in soil carbon sequestration has been increasingly recognized. However, the mechanism by which mineral-associated organic matter (MAOM) resists microbial decomposition remains an open question. We prepared MAOM on amorphous allophane and crystalline kaolinite with different organic matter (OM) proxies, characterized the affinity strength of these associations using isothermal titration calorimetry and X-ray photoelectron spectroscopy, and quantified their microbial mineralization through aerobic incubation. We found that amorphous allophane displayed greater OM adsorption capacity due to its higher specific surface area; in contrast, crystalline kaolinite exhibited stronger binding with OM, consistent with its predominant inner-sphere complexation. Furthermore, lower MAOM mineralization was found corresponding to higher Langmuir affinity. This inverse relationship was more pronounced than the correlation with the amount of OM adsorbed by minerals. These findings suggest that the overall MAOM stability is controlled by a balance between binding strength and adsorption capacity. Namely, stronger binding affinity enhances microbial resistance of MAOM, while the abundance of mineral sites determines the amount of MAOM accessible for microbial decomposition. This study presents a novel mechanistic understanding of the MAOM dynamics and refines the prevailing perspective on MAOM persistence.

Journal Articles

Neutronic characteristics of a partially damaged reactor model with varying numbers of damaged fuel assemblies

Nguyen, H. H.

Annals of Nuclear Energy, 230, p.112171_1 - 112171_13, 2026/06

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

This study examined the effects of the moderator-to-fuel volume ratio, fuel debris shape, and the number of damaged fuel assemblies on the neutronic characteristics of a partially damaged reactor model, where the fuel assemblies at the core center melt to fuel debris while the fuel assemblies at the outer region remain intact. The investigations were conducted using the Serpent code and the JENDL-5 library. The results show that when fuel debris is surrounded by intact fuel assemblies, the k$$_{rm eff}$$ can be classified into two groups based on the shape of the fuel debris. Conversely, in scenarios where the fuel debris is not fully encircled by intact fuel assemblies, the shape of the fuel debris has a negligible impact on the k$$_{rm eff}$$. Additionally, the relationship between the number of neutrons entering and leaving the fuel debris determines how the shape of the fuel debris affects the k$$_{rm eff}$$.

Journal Articles

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

Taniguchi, Yoshinori; Luu, V. N.; Tasaki, Yudai; Udagawa, Yutaka; Katsuyama, Jinya

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

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

Journal Articles

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

Luu, V. N.; Taniguchi, Yoshinori; Udagawa, Yutaka; Tasaki, Yudai; Katsuyama, Jinya

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

 Times Cited Count:1 Percentile:96.95(Nuclear Science & Technology)

Journal Articles

Potential and solution conductivity inside stainless steel crevices in a very dilute bulk solution

Soma, Yasutaka; Komatsu, Atsushi; Igarashi, Takahiro

Corrosion Science, 265, p.113182_1 - 113182_13, 2026/06

Journal Articles

No detectable impact of ALPS-treated water discharge on tritium levels in terrestrial waters of the upper Ota River catchment, Fukushima, Japan

Sakuma, Kazuyuki; Yoshimura, Kazuya

Journal of Environmental Radioactivity, 297, p.108055_1 - 108055_4, 2026/06

Tritium ($$^{3}$$H) is the principal radionuclide remaining in ALPS-treated water discharged from the Fukushima Dai-ichi Nuclear Power Plant (FDNPP), and its potential environmental impact has drawn considerable attention. To evaluate possible terrestrial effects, $$^{3}$$H concentrations were monitored in precipitation, groundwater, and river water in the upper Ota River catchment in Fukushima Prefecture. Monthly samples were collected before and after the initiation of oceanic discharge in August 2023. Time-series comparison showed no discernible increase in $$^{3}$$H concentrations after the start of discharge for any water type. Non-parametric statistical analysis further confirmed the absence of significant differences for groundwater and river water. Observed variations were consistent with natural background levels and known seasonal patterns in precipitation in Japan. These results indicate that ALPS-treated water discharge has had no detectable impact on terrestrial waters in the study area.

Journal Articles

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

Miyazaki, Kanako*; Fueda, Kazuki*; Kadowaki, Masanao; Terada, Hiroaki; Kozai, Naofumi; Iwata, Hajime; Horie, Kenji*; Takehara, Mami*; Yamasaki, Shinya*; Grambow, B.*; et al.

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

Journal Articles

Bayesian approach to model temperature dependence of Charpy absorbed energy and uncertainty evaluation of ductile-to-brittle transition temperature for reactor pressure vessel steel

Takamizawa, Hisashi; Nishiyama, Yutaka

Journal of Pressure Vessel Technology, 148(3), p.031501_1 - 031502_12, 2026/06

Embrittlement of reactor pressure vessel (RPV) steel caused by neutron irradiation has been evaluated using ductile-to-brittle transition temperature (DBTT) derived from surveillance tests (Charpy impact tests) during plant operation. For reliable structural integrity assessment of the RPV, incorporating adequate safety margins which take into account uncertainties inherent in surveillance Charpy impact tests is needed. In this study, a model to evaluate temperature dependence of Charpy absorbed energy variability using approximately 1,900 datasets of unirradiated and irradiated materials manufactured in Japan and United States was developed. Next, probability distribution of Charpy ductile-to-brittle transition temperature at a 41J energy level ($$T$$$$_{rm 41J}$$) was evaluated by estimating the probability distribution of Charpy test data using Monte Carlo sampling and Bayesian inference. From the detailed evaluation of the relationship between the number of specimens and $$T$$$$_{rm 41J}$$ uncertainty, uncertainty of $$T$$$$_{rm 41J}$$ was found to be almost the same in materials manufactured in Japan and U.S., and unchanged with neutron irradiation (no clear change in material inhomogeneity). Regarding product form on the other hand, uncertainty of $$T$$$$_{rm 41J}$$ for base metal and weld metal was almost the same, but the heat affected zone was shown to have large uncertainty.

Journal Articles

Implementation of a new function for handling nuclear data of outgoing particles and residual excitation states in PHITS

Furuta, Takuya; Hashimoto, Shintaro; Ogawa, Tatsuhiko; Tanimura, Yoshihiko

Nuclear Instruments and Methods in Physics Research A, 1086, p.171320_1 - 171320_8, 2026/06

 Times Cited Count:0 Percentile:0.00(Instruments & Instrumentation)

A new function to incorporate nuclear data libraries with outgoing particles plus residual nuclei in specific excitation states for neutron-induced reactions has been implemented in a Monte Carlo simulation code, Particle and Heavy Ion Transport code System (PHITS). With this function, accurate predictions of outgoing particle spectra and angular distributions according to the nuclear data libraries become possible, while accounting for production of residual nuclei and de-excitation gammas, conserving total energy and momentum in each event. This feature allows users to perform high-precision simulations of detector responses and radiation damage in materials.

Journal Articles

Transient behavior of a boiling water reactor-type offshore floating nuclear power plant during platform motion

Fukuda, Kodai; Obara, Toru*

Nuclear Technology, 212(6), p.1567 - 1578, 2026/06

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

JAEA Reports

Seismic reinforcement work of the Waste Treatment Facility No. 1 and the incinerator

Mori, Masakazu; Endo, Masayuki; Seya, Manato; Hozumi, Shinsei; Sudo, Tomoyuki

JAEA-Technology 2026-002, 33 Pages, 2026/05

JAEA-Technology-2026-002.pdf:2.01MB

The Waste Treatment Facility No. 1 is equipped with an incinerator for the treatment of radioactive combustible solid waste generated from facilities at the Nuclear Science Research Institute. To obtain conformity confirmation with the New Regulatory Requirements, seismic evaluations were conducted on the facility's building and its incineration equipment. As a result, neither the building nor the equipment satisfied the required seismic standards. Therefore, seismic reinforcement work for the building and equipment was carried out from April 2018 to March 2019. This report outlines the results of seismic evaluation and design, as well as the construction process and safety management during the seismic reinforcement work.

JAEA Reports

Malfunction and repair of JMTR facility blower (AC-1)

Kuwabara, Ryota; Kagi, Takumi; Yanai, Tomohiro; Watahiki, Shunsuke

JAEA-Review 2026-002, 21 Pages, 2026/05

JAEA-Review-2026-002.pdf:2.72MB

The JMTR (Materials Testing Reactor) nuclear facility was established and operated for the purpose of conducting irradiation experiments on reactor materials and fuels to establish domestic power reactor technology and produce radioisotopes. In the "Mid- to Long-Term Facility Management Plan" formulated by Japan Atomic Energy Agency in April 2017, JMTR was designated as a facility subject to decommissioning. In September 2019, the Agency submitted a decommissioning plan approval application to the Nuclear Regulation Authority, which was granted in March 2021. As the first step of the decommissioning plan, non-controlled area equipment removal and transportation of spent fuel elements to the United States are currently underway. The AC-1 blower, part of the JMTR reactor building ventilation system, is classified as a performance-maintenance equipment item under the decommissioning plan. Accordingly, in accordance with safety regulations, the equipment undergoes regular inspections, testing, and calibration at appropriate intervals to ensure the maintenance of necessary functions and performance for safety purposes. However, two malfunction events have occurred in the past: a grease leakage incident near the bearing on the load side of the blower fin-frame motor in 2021, and a wear confirmation incident on the blower shaft in 2024. This report summarizes the malfunction events involving bearing and shaft components of both the electric motor and blower within the performance-maintenance equipment of the decommissioning facility, JMTR, as well as the on-site repairs conducted for these problematic areas.

100093 (Records 1-20 displayed on this page)