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under high temperatures and various water vapor concentrationsMohamad, A. B.; Nakajima, Kunihisa; Imoto, Jumpei*; Takano, Masahide
Journal of Nuclear Materials, 631, p.156826_1 - 156826_12, 2026/09
Times Cited Count:0Shi, 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
-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
(no regularization), hotspot locations fluctuate significantly, with quantitative mean absolute error fluctuations at around
, whereas
yields improved spatial consistency and the fluctuation quantities decrease to the
range. Comparative analysis identifies
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.
Ishida, Reiya; Aoki, Emi; Sonobe, Hiroshi; Oto, Tsutomu; Kimura, Akihiro
JAEA-Review 2026-019, 50 Pages, 2026/07
Subsequent to a leakage incident in October 2012 involving the SFC waste liquid transfer piping in the C Trench, additional leakage incidents occurred in the No. 4 drainage system piping and the SFC waste resin transfer piping. Furthermore, leakage incidents occurred in the tank yard, including seepage at welded joints in the waste liquid piping, as well as leakage from the waste liquid tanks. Since these incidents, the transfer of liquid waste from the hot laboratory facility to the JMTR tank yard has been suspended. Currently, as the waste liquid piping in the JMTR tank yard and the waste liquid tanks receiving liquid waste from the hot laboratory have been replaced and in sound condition, a plans is being developed to resume liquid waste transfer. To confirm the integrity of the waste liquid piping system, which runs from the hot laboratory through the C Trench to the tank yard, radiographic testing (hereafter referred to as "RT") of the pipe welds will be conducted. As it has been confirmed that the waste liquid piping is wrapped with asbestos-containing thermal insulation materials, these materials will be removed from the piping prior to RT. During this removal work, it is essential to comply with applicable laws and regulations and to ensure worker safety. This report summarizes the plan for removal of asbestos-containing thermal insulation materials in radiation controlled areas in order to minimize asbestos-related risks, as well as the procedures for the removal work and the methods for storage management.
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(Nuclear Science & Technology)Matsumoto, Chihiro*; Tanabe, Shota*; Chika, Yamamoto*; Zhao, T.*; Sawano, Toyoaki*; Nonaka, Saori*; Kato, Hideyuki*; Yamaguchi, Fumie; Takahara, Shogo; Tanaka, Tomoaki*; et al.
Journal of Radiological Protection, 46(3), p.032501_1 - 032501_10, 2026/07

Minami, Shoko*; Matsuno, Haruki*; Morita, Kyohei*; Matsuki, Rintaro*; Kotegawa, Hisashi*; Harima, Hisatomo*; Haga, Yoshinori; Yamamoto, Etsuji; Onuki, Yoshichika*; Tou, Hideki*
Journal of the Physical Society of Japan, 95(7), p.074711_1 - 074711_11, 2026/07
Soma, Yasutaka; Komatsu, Atsushi; Igarashi, Takahiro
Corrosion Science, 265, p.113182_1 - 113182_13, 2026/06
Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)
Zr(n,
)
Zr and
Zr(n,
)
Zr reactions at JRR-3Nakamura, Shoji; Kimura, Atsushi; Endo, Shunsuke; Rovira Leveroni, G.; Shibahara, Yuji*
Journal of Nuclear Science and Technology, 63(6), p.653 - 666, 2026/06
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)
/Pu
couple in NaCl-2CsCl meltHayashi, Hirokazu; Minato, Kazuo*
Journal of Radioanalytical and Nuclear Chemistry, 335(6), p.4233 - 4240, 2026/06
Times Cited Count:0 Percentile:0.00(Chemistry, Analytical)Anhydrous plutonium trichloride (PuCl
) was synthesized by a solid-state reaction of plutonium nitride with cadmium chloride. The lattice constants of hexagonal PuCl
were refined from its powder X-ray diffraction pattern to be a = 0.7394
0.0006 nm and c = 0.4244
0.0006 nm, which are close to the reported values. Using the synthesized PuCl
sample, electrochemical behavior of plutonium in NaCl-2CsCl melt at 823-923 K was investigated by cyclic voltammetry and open-circuit chronopotentiometry after polarization. The results show that Pu
ions are reduced to Pu metal by single-step mechanism in the NaCl-2CsCl melt. The apparent standard potentials of Pu
/Pu
redox couple were determined to be E
(Pu
/Pu
) = -3.514 + 8.60
10
T vs. Cl
/Cl
(V). The activity coefficients of Pu
ions were determined using the previously reported Gibbs free energy of formation for PuCl
in the supercooled liquid state.
Nakamura, Shoji; Shibahara, Yuji*; Kimura, Atsushi; Endo, Shunsuke; Rovira Leveroni, G.
KURNS Progress Report 2025, P. 101, 2026/06
no abstracts in English
Fukuda, Kodai; Obara, Toru*
Nuclear Technology, 212(6), p.1567 - 1578, 2026/06
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)Kawabe, Tomosaburo*; Sano, Yoshihiko*; Kuwahara, Fujio*; Uesawa, Shinichiro; Yoshida, Hiroyuki
Dai-63-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu (Internet), 1 Pages, 2026/05
To estimate the thermal behavior of fuel debris inside the Primary Containment Vessels (PCVs) of TEPCO's Fukushima Daiichi Nuclear Power Station, a simulation method has been developed using the JUPITER code with porous medium models. However, it has been found that the selection of models and parameters according to the internal structure of the porous media significantly affects the accuracy of simulation results, highlighting the need for appropriate model selection strategies. In this study, we focus on packed beds with particles as one form of porous media and investigate a methodology for determining model parameters that characterize their flow behavior. Systematic knowledge of packed beds with heterogeneous particle size ratios and packing structures remains limited, and comprehensive organization accounting for structural differences has not yet been fully established. Therefore, numerical simulations were employed to evaluate the permeability and Forchheimer coefficient of packed beds with different particle size ratios and packing structures. Based on the obtained results, a method for appropriately determining these parameters according to the structural characteristics of packed beds is proposed, and insights are provided that contribute to improving the accuracy of flow analysis models in porous media.
Ishi, Yoshihiro*; Uesugi, Tomonori*; Mori, Yoshiharu*; Nishio, Katsuhisa
Physical Review Accelerators and Beams (Internet), 29(5), p.050101_1 - 050101_14, 2026/05
Times Cited Count:0 Percentile:0.00(Physics, Nuclear)Shiotsu, Hiroyuki
Progress in Nuclear Energy, 195, p.106300_1 - 106300_11, 2026/05
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)Noseck, U.*; Sch
fer, T.*; Alonso, U.*; Hamamoto, Takafumi*; Havlova, V.*; Hibberd, R.*; Ishidera, Takamitsu; Kitamura, Akira; Klajmon, M.*; Missana, T.*; et al.
Applied Geochemistry, 201, p.106762_1 - 106762_23, 2026/04
Times Cited Count:0 Percentile:0.00(Geochemistry & Geophysics)Thermodynamic benchmark calculations have been performed to better understand the behavior of
Se(VI),
Tc(VII),
U(VI),
Np(V),
Am(III), Th(IV) and
Pu(IV)) in the evolving geochemical conditions of the Long-term In-situ Test (LIT) at the Grimsel Test Site (GTS) and corresponding mock-up experiment. It also aims to identify the status of the geochemical speciation models and databases for these elements. The experiments are simulating the near-field conditions in some radioactive waste repository concept including a bentonite engineered barrier emplaced in crystalline rock and the findings are contributing to the long-term safety assessment of these facilities.
Ebihara, Kenichi; Yamaguchi, Masatake; Itakura, Mitsuhiro
Metallurgical and Materials Transactions A, 57(4), p.1480 - 1489, 2026/04
Times Cited Count:0 Percentile:0.00(Materials Science, Multidisciplinary)Hydrogen (H) embrittlement is an important issue for steel. The experimental thermal desorption spectra of H from an iron sample containing H-enhanced strain-induced vacancies (Vs) were successfully reproduced by revising a previous numerical model. In the revised model, we adopted concentration variables for Vs and V clusters, which are distinguished by the number of trapped H atoms. This revision eliminated the assumption of V and V cluster migration, required in the original model. Simulation results of the revised model revealed that the spike-like desorption on the peak attributed to Vs and V clusters in the spectra simulated by the original model was an artifact caused by the assumption. In addition, it was suggested that V clusters can exist other than Vs in the specimens after deformation with H charging. It is considered that the revised model is a useful framework for studying Vs and V clusters under H-affected conditions.
Sakakibara, Ryotaro*; Terasawa, Tomoo; Kawauchi, Taizo*; Fukutani, Katsuyuki; Ito, Takahiro*; Norimatsu, Wataru*
Small Methods, 10(8), p.e01889_1 - e01889_12, 2026/04
Times Cited Count:0 Percentile:0.00(Chemistry, Physical)Group for Fukushima Mapping Project
JAEA-Technology 2025-013, 206 Pages, 2026/03
This report presents results of the investigations on the distribution-mapping project of radioactive substances conducted in FY2024. Car-borne and walk surveys, a measurement using survey meters, and an unmanned helicopter survey were carried out to obtain air dose rate data on land to create their distribution maps, and temporal changes of those air dose rates were analyzed. In order to confirm the applicability of unmanned aircraft to monitoring in mountainous areas, a basic performance of unmanned aircraft was investigated in mountainous areas. Surveys on depth profile of radiocesium and in-situ measurements as for radiocesium deposition were performed. These measurement results were published on the WEB site. Based on these measurement results, effective half-lives of the temporal changes in the air dose rates and the deposition were evaluated. Using the Bayesian hierarchical modeling approach, we obtained maps that integrated air dose rate distribution data acquired through surveys such as car-borne and walk surveys. Radiation monitoring and analysis of environmental samples owing to the comprehensive radiation monitoring plan were carried out. Representative life patterns that can be expected after the return to the evacuation-designated restricted area were set, and the cumulative exposure doses were evaluated for the local governments and residents in the area. Score maps to classify the importance of the measurement points were created, and the temporal changes in the score were analyzed. A system to report the tritium concentration level in seawater to the Nuclear Regulation Authority was operated, and the variation of tritium concentration before and after the discharge of ALPS treated water to the ocean was analyzed. Monitoring data in coastal area performed owing to the comprehensive radiation monitoring plan until FY2024 was analyzed.
Yamashita, Hayato; Toyota, Kodai; Onizawa, Takashi; Yamamoto, Kenji*; Kubo, Koji*
Nihon Kikai Gakkai Rombunshu (Internet), 92(955), p.25-00176_1 - 25-00176_13, 2026/03
It is planned that Mod.9Cr-1Mo steel will be used as the structural material for the steam generator of the demonstration fast reactor. Creep strength of welded joints of Mod.9Cr-1Mo steel is lower than that of base metal at high temperature and long time. In addition, the creep strength of welded joints of Mod.9Cr-1Mo steel with repair welding is lower than that of without repair welding. In this study, the effects of the location and number of repair welds performed on the creep strength of welded joints of Mod.9Cr-1Mo steel were investigated, and a repair welding method was developed for the construction of the demonstration fast reactor. It was clarified that, regardless of the location and number of repair welds performed, the degradation in creep strength could be greatly reduced by performing the repair welding before post weld heat treatment (PWHT). Furthermore, it was found that the superposition of thermal history and the formation of a heat affected zone (HAZ) on the weld metal promote the coarsening of ferrite grains during creep and cause a slight reduction in creep strength. All repair welding was performed prior to PWHT, and a repair welding method was also developed to minimize thermal history superposition and weld metal HAZ formation.
pyrochlore antiferromagnet NaCdCu
F
Kancko, A.*; Sakai, Hironori; Tokunaga, Yo; Colman, R. H.*; 6 of others*
Physical Review Research (Internet), 8(1), p.013344_1 - 013344_11, 2026/03