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Aizawa, Naoto*; Watanabe, Tomoaki; Chiba, Go*; Tada, Kenichi; Fujita, Tatsuya*; Yamamoto, Akio*
Nuclear Engineering and Technology, 58(5), p.104176_1 - 104176_16, 2026/05
Times Cited Count:0 Percentile:0.00
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modelKikuchi, Norihiro; Imai, Yasutomo*; Yoshikawa, Ryuji; Tanaka, Masaaki; Ohshima, Hiroyuki
JAEA-Data/Code 2025-017, 133 Pages, 2026/03
In a core design of sodium-cooled fast reactors (SFRs), it is necessary to confirm the integrity of fuel assemblies (FAs) in the core over a wide range of operating conditions. To evaluate the velocity and temperature distributions within the FAs in detail, we have been developing a detailed FA thermal-hydraulic analysis code named SPIRAL. In our previous works, we implemented numerical methods for fluid mechanics at isothermal conditions and turbulence models. Subsequently, we implemented turbulent heat transfer models for the evaluation of temperature distribution within the FAs, and validated them through experimental analyses mainly under high flow rate conditions. The thermal-hydraulics within the FAs varies depending on the operating conditions. Furthermore, the local Reynolds (Re) number within the FAs varies widely due to the influence of wire spacers spirally wound around the fuel rod. For this reason, it has been shown that standard and low Re number k-
/k
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models have difficulty reproducing the thermal-hydraulics in the laminar-turbulent transition region. Therefore, to reproduce the thermal-hydraulics over a wide Re number range, we developed a hybrid k-
/k
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model that combines the standard k-
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model with the advantages of the low Re number k-
/k
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model. This paper describes the governing equations, constitutive equations derived from various turbulence models, their formularizations by the finite element method, their numerical treatment, and the treatment of boundary conditions. We also report the results of analyses conducted to validate the hybrid k-
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model for predicting pressure drop and temperature distribution.
years considering uncertainty of sea level changeTakai, Shizuka; Uchikoshi, Emiko*; Shimada, Taro; Takeda, Seiji
MRS Advances (Internet), 6 Pages, 2026/00
In Japan, regulations require the disposal of intermediate-level radioactive waste at depths of at least 70 m below ground surface for 10
years. Therefore, it is essential to assess the long-term safety of landscape evolution by uplift, denudation, and sea-level change, which will decrease the depth of disposal and change groundwater flow. Numerical simulations are invaluable for analyzing landscape evolution while taking into account future uncertainties. However, the projection over the next 10
years has not been conducted for coastal areas, which are preferable to disposal in terms of waste transportation. In this study, we developed a framework for projection of coastal landscape evolution on a 10
years based on simulations over the past 125,000 years. Using the LEMs developed by JAEA, the constructed framework following two steps was verified in the Kamikita coastal plain. Step 1) Simulation from past to present: Based on simulations of the past 125,000 years (the last glacial-interglacial cycle), we first identified the best parameter set that can reproduce the actual topography. The deviation between reproduced and recent topography is within
15 m for 80% of the area. Step 2) Projection over the next 10
years: Using the best parameters, we make projections over the next 125,000 years. On the basis of sea level change in the late Quaternary and previous research on the glacial isostatic adjustment modelling, three scenarios of future global sea level were considered; base case (the next glacial period starts 5,000 years after present), glacial case (the next glacial period starts from the present), and global warming case (the current interglacial lasts over the next 125,000 years). In the case of a hypothetical disposal depth of 100 m, erosion depth should be less than 30 m to maintain the waste at a depth of 70 m below ground. For the next 125,000 years, erosion exceeding 30 m is projected to occur in the river (mid and downstream) and coastal areas (~below highest projected sea level of 15 m). Vertical erosion by fluvial incision is the most affected by sea level decline. In the base and global warming cases, sea level rises up to 15 m; erosion occurs several hundred meters landward from the current 15-m contour. We also confirmed that the average basin relief increases significantly in accordance with sea level fall.
Sato, Kaoru
Isotope News, (801), p.6 - 9, 2025/10
In 2012, ICRP recommended the latest scientific knowledge on radiation protection for the stem cells. Body size affects exposure doses, so the differences in body sizes between Japanese and Caucasians must be considered in dose assessments. Previously, there were no adult Japanese human models incorporating the stem cell regions. Therefore, we developed polygon mesh-type human models of the average adult Japanese male (JPM) and female (JPF) to analyze exposure doses considering Japanese body characteristics. We have completed these models by defining stem cells within organs like the alimentary tracts, urinary bladder, and lens, using image processing. The JPM and JPF are the only human models that can evaluate exposure doses to organs and its stem cells, considering the body characteristics of the Japanese. They are expected to be useful for optimizing exposure management in the medical and nuclear fields. This paper provides an overview of the JPM and JPF.
Kim, M.
Kankyo Sozo Senta Chosa Kenkyu Seika Hokokusho, Heisei 27-Nendo (2015)
Reiwa 6-Nendo (2024) (Internet), P. 31, 2025/10
3D-Air Dose Rate Evaluation System has been developed that can accurately estimate complex spatial dose rate distributions due to radiation emitted into the environment. The applicability of the system was examined, and the results of the analysis and measurements were in general agreement.
Sano, Yoshihiko*; Ota, Kensuke*; Kuwahara, Fujio*; Uesawa, Shinichiro; Yoshida, Hiroyuki
Nihon Kikai Gakkai Netsu Kogaku Konfuarensu 2025 Koen Rombunshu, 1 Pages, 2025/10
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 investigated methods for calculating macroscopic model constants that characterize flow behavior in porous media. These properties are influenced not only by the volume ratio of solid and gas phases but also by the structural features of the porous media. Focusing on packed beds composed of particles with varying diameters, we conducted numerical simulations to evaluate permeability and Forchheimer coefficient across diverse structural configurations. Based on the results, we propose a method for appropriately determining these parameters according to the structure of the packed bed, thereby contributing to the improvement of the porous media heat transfer and flow model.
Choi, B.; Nishida, Akemi; Tsutsumi, Hideaki*; Takada, Tsuyoshi
Transactions of the 28th International Conference on Structural Mechanics in Reactor Technology (SMiRT28) (Internet), 10 Pages, 2025/08
One of the key lessons learned from the Fukushima Daiichi Nuclear Power Plant accident is the necessity of developing a probabilistic risk assessment (PRA) method that considers multiple external hazards (multi-hazards), such as earthquakes and tsunamis. In this study, we organized classification concepts for multi-hazards that could lead to significant disasters. A classification method for multi-hazard scenarios was developed based on causal relationships (dependent or independent) and temporal relationships (simultaneous or time-lagged occurrence). Furthermore, we examined modeling approaches for multi-hazard scenarios using the developed classification method. The modeling considered elements such as hazard curves, hazard intensity, hazard frequency, time, and event duration, and these were defined in terms of conditional probability density functions. This paper reports application examples of multi-hazard evaluation under hypothetical site and analysis conditions, focusing on representative scenarios such as earthquake-tornado and earthquake-tsunami combinations, based on the multi-hazard classification method developed in previous studies.
Uesawa, Shinichiro; Yamashita, Susumu; Sano, Yoshihiko*; Yoshida, Hiroyuki
Journal of Nuclear Science and Technology, 62(6), p.523 - 541, 2025/06
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)Japan Atomic Energy Agency (JAEA) has developed a numerical method with the JUPITER code with a porous medium model to calculate the thermal behavior in PCVs of 1F. In this study, we performed an experiment and numerical simulation of the natural convective heat transfer with the porous medium to validate JUPITER with the porous medium model. In comparison of the temperature and velocity distributions between the experiment and simulation, the temperature distribution in the simulation was in good agreement with the distribution in the experiment except the temperature near the top surface of the porous medium. The velocity distribution also agreed qualitatively with the experimental result. In addition, we also performed the numerical simulations with various effective thermal conductivity models to discuss the effect of the conductivity based on the internal structure of porous media on the natural convective heat transfer. The result indicated that the temperature distribution in the porous medium and the velocity distribution of the natural convection were significantly different for each model, and thus the conductivity of the fuel debris was one of the key parameters of in the thermal behavior analysis in 1F.
Watanabe, Tomoaki; Aizawa, Naoto*; Chiba, Go*; Tada, Kenichi; Yamamoto, Akio*
Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025) (Internet), p.288 - 297, 2025/04
Currently, a major burnup calculation method for the nuclide composition of nuclear fuel conducts neutron transport calculations at each burnup step to account for changes in the neutron spectrum. While this method is highly accurate, the large computational cost of neutron transport calculations can be problematic. Therefore, a fast burnup calculation method based on neutron spectrum reconstruction with the proper orthogonal decomposition (POD) and regression model is investigated. In this method, dimensionality reduction by POD is applied to many neutron fluxes obtained from detailed burnup calculations for various input parameter sets, and regression models are constructed to connect the dimensionality-reduced neutron fluxes and parameters. By substituting arbitrary input parameters to the regression models, the neutron flux is reconstructed and the burnup calculation is performed. This method performs burnup calculations that consider changes in the neutron spectrum based on input conditions without neutron transport calculations. The present method was applied to a PWR UO
fuel pin cell model. The results show the nuclide inventory can be calculated with a prediction accuracy within a few percent. In addition, it is found that the calculation error is dominated by the regression models, which implies the further improvement of the regression models leads to improving the accuracy.
Saito, Shota; Kimura, Masanori; Hiraoka, Hirokazu
Kotsu Kogaku Kenkyu Happyokai Koenshu, 45, p.844 - 849, 2025/00
no abstracts in English
Kimura, Yoshiki; Matsumoto, Tetsuya*; Yamaguchi, Tomoki
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
no abstracts in English
Soma, Yasutaka; Komatsu, Atsushi; Igarashi, Takahiro
Dai-71-Kai Zairyo To Kankyo Toronkai Koenshu (CD-ROM), p.253 - 256, 2024/11
In our previous study, we reported that Cl ions penetrating stainless steel crevices do not dissipate by diffusion, even in high-purity water (i.e., conductivity remains stable), likely due to electrochemical reactions inside and outside the crevice. This study further analyzes ion behavior by experimentally and computationally investigating ion concentration drivers in high-purity water. Results show that, at 50
C, the crevice conductivity of SUS316L stainless steel reached 100
S/cm (100-1000 times bulk water). Modeling suggests this is due to metal cations and hydroxide ions from dissolved oxygen reduction. The dissolution rate was estimated at 10nA/cm
.
Choi, B.; Nishida, Akemi; Tsutsumi, Hideaki*; Takada, Tsuyoshi
Proceedings of Probabilistic Safety Assessment and Management & Asian Symposium on Risk Assessment and Management (PSAM17 & ASRAM2024) (Internet), 8 Pages, 2024/10
The Fukushima Daiichi Nuclear Power Plant accident highlighted the importance of developing safety assessment methods that consider multihazard events involving numerous simultaneously occurring events such as earthquakes (shaking) and tsunamis (submersion). When addressing such multihazard events, traditional methods often focus on assessing the load combinations of general structures in their structural designs and adopt simple selection criteria. However, these methods fall short when evaluating, countering, and screening external events, such as earthquakes, tsunamis, strong winds, and concentrated heavy rainfall, that occur simultaneously or in a chain. To address this, we reviewed existing literature on multihazard assessment methods, focusing particularly on scenarios involving earthquake and tsunami events. Based on concepts and basic theories, we examined various methods for addressing multihazard scenarios and classified their characteristics. Specifically, several multihazard scenarios were surveyed, and the relationships between multiple hazards were organized. In addition, common causes leading to combined events, their mutual influences, and potential cascading effects were analyzed.
for brittle fracture in ductile-brittle transition temperature regionHojo, Kiminobu*; Hirota, Takatoshi*; Nagoshi, Yasuto*; Fukahori, Takuya*; Shimizu, Kazuma*; Shimodaira, Masaki; Ogawa, Takuya*; Yashirodai, Kenji*; Ohata, Mitsuru*; Minami, Fumiyoshi*
Proceedings of the ASME 2024 Pressure Vessels & Piping Conference (PVP 2024) (Internet), 9 Pages, 2024/07
no abstracts in English
Kikuchi, Hirohito*; Uda, Toshiaki*; Hayashi, Daisuke*; Emori, Minoru*; Kimura, Shun
Genshiryoku Bakkuendo Kenkyu (CD-ROM), 31(1), p.11 - 20, 2024/06
no abstracts in English
Abe, Shinichiro
Kaku Deta Nyusu (Internet), (138), p.24 - 31, 2024/06
Recently, muons are applied to various kinds of research fields, and the development of muon nuclear data is considered. The model for negative muon capture reaction implemented in PHITS has been underestimate the measured data for productions of secondary light particles. We applied the surface coalescence model (SCM) to the JQMD model and implemented the effect of meson exchange current (MEC) in the excitation function. The SCM improved productions of light complex particles, and the consideration of the MEC process in the excitation function improved productions of high energy nucleons. The improved model was applied to the soft error simulation. It was found that SEU event cross sections increase about 10
50% when the negative muon stop around the memory array.
Takasaki, Koji
Hokeikyo Nyusu, (73), p.2 - 5, 2024/04
The development of radiation measurement and digital technology for the decommissioning of the Fukushima Daiichi Nuclear Power Plant, which is being conducted by the Remote System and Sensing Technology Division of CLADS, will be presented.
Kim, M.; Yoshimura, Kazuya; Sakuma, Kazuyuki; Malins, A.*; Abe, Tomohisa; Nakama, Shigeo; Machida, Masahiko; Saito, Kimiaki
Kankyo Hoshano Josen Gakkai-Shi, 12(2), p.39 - 53, 2024/04
More than ten years have passed since the accident at TEPCO's Fukushima Daiichi Nuclear Power Station. But with the progress of decontamination, the evacuation order has been lifted and the return of residents is still ongoing. Under these circumstances, in order to quantitatively evaluate the effect of decontamination activities and cultivation on air dose rate reduction, a detailed environmental model was constructed using 3D-ADRES for a real area located in the Okuma town, Fukushima prefecture. Monte Carlo simulations were performed using the model to calculate realistic distributions of radioactive Cs based on measurement results and air dose rates reflecting changes over time. As a result, the distribution of air dose rates at 100 cm above ground level in the target area according to decontamination and cultivation activities was calculated. The calculated air dose rates reproduced the measured values well, and were confirmed to be appropriate as a method for evaluating the effects of decontamination and cultivation activities. This method is expected to serve as a reference for further decontamination management measures to reduce the air dose rate in the difficult-to-return zone, where entry is still restricted.
Aoyagi, Kazuhei; Ishii, Eiichi
Environmental Earth Sciences, 83(3), p.98_1 - 98_15, 2024/02
Times Cited Count:2 Percentile:25.65(Environmental Sciences)The long-term geological disposal of high-level radioactive waste relies on predictions of future changes in a disposal facility's hydro-mechanical characteristics to assess potential leakage through fractures in the excavation damaged zone (EDZ) after backfilling the facility. This study evaluated the transmissivity of EDZ fractures using in situ hydraulic tests around the area of a full-scale, experimental, engineered barrier system in the Horonobe Underground Research Laboratory, Hokkaido, Japan. After their installation, the buffer blocks swelled, altering the stresses within the EDZ fractures. The effects of these changing stresses on the fractures' transmissivity were assessed over a period of 4 years. The transmissivity continuously decreased in this period to about 41% of its value measured prior to the swelling. Using the Barton-Bandis normal-stress-dependent fracture-closure model, the decrease in transmissivity is quantitatively attributed to closure of the EDZ fractures, which was caused by the swelling pressure increasing up to 0.88 MPa. Evidence of fracture closure came from seismic tomography surveying, which revealed a slight increase in seismic velocity in the study area with increasing swelling pressure. The results show that EDZ fractures were closed by swelling of the full-scale buffer material. They also demonstrate the applicability of the Barton-Bandis model to preliminary estimation of the long-term transmissivity of EDZ fractures in facilities for the geological disposal of radioactive waste.
Terada, Hiroaki
Ten Hasseigen Karano Mesosukeru Kakusan Shumireshon; Fukushima Daiichi Genshiryoku Hatsudensho Jiko O Fumaete (Kisho Kenkyu Noto Dai-248-Go), p.115 - 121, 2023/09
no abstracts in English