Development of mesh generation method in a fast reactor fuel assembly

Kikuchi, Norihiro; Imai, Yasutomo*; Yoshikawa, Ryuji; Tanaka, Masaaki; Ohshima, Hiroyuki

JAEA-Data/Code 2025-018, 96 Pages, 2026/03

JAEA-Data-Code-2025-018.pdf:5.54MB

In the Japan Atomic Energy Agency, a detailed thermal-hydraulic analysis code named SPIRAL based on the finite element method (FEM) is being developed to evaluate the detailed thermal-hydraulic properties of fuel assemblies (FAs) in sodium-cooled fast reactors (FBRs). Because the quality of the computational grid (elements) used in the calculations has a significant impact on the prediction accuracy, the allocation of high-quality elements in the wire-spacer-type FA pin bundle region is an important issue for numerical analysis. Although a commercial mesh generation program (mesher) with CAD data of FA's geometric shape can be considered as one measure, it is an extremely complicated task to perform element division of complex FA region. Therefore, to efficiently allocate high-quality elements, we developed a mesher that automatically performs element division in the FA region using the FA's geometric shape (design information) and meshing parameters as input conditions. This report describes the details of the mesher's various meshing models and their usage. To regularly allocate the computational grid for the complex FA region, the mesher first divides the region into multiple blocks using a multi-block method, then generates boundary-fitted curvilinear coordinate grids for each block region, and finally integrates them into a single FA mesh system. In addition, a combination of hexahedral elements and prism-shaped elements is arranged to maintain element continuity between adjacent block regions. Element division for both the normal FAs surrounded by a hexagonal cross-section tube and the irregular FAs, inside which a duct is installed to promote the discharge of molten fuel, is possible. The development of this mesher has made it possible to accurately and efficiently perform element division of complex FA region on various conditions.

Development of HCl-free solid-phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides, 4; Rapid determination of Pd in concrete rubble

Ota, Yuki; Do, V.-K.; Banjarnahor, I. M.; Iwahashi, Hiroyuki; Furuse, Takahiro; Tanaka, Kosuke

Journal of Radioanalytical and Nuclear Chemistry, 335(1), p.939 - 948, 2026/02

https://doi.org/10.1007/s10967-026-10735-0

Speciation of cesium in a radiocesium-bearing microparticle emitted from Unit 1 during the Fukushima nuclear accident by XANES spectroscopy using transition edge sensor

Takahashi, Yoshio*; Miura, Hikaru*; Yamada, Shinya*; Sekizawa, Oki*; Nitta, Kiyofumi*; Hashimoto, Tadashi*; Yomogida, Takumi; Yamaguchi, Akiko; Okada, Shinji*; Itai, Takaaki*; et al.

Journal of Hazardous Materials, 495, p.139031_1 - 139031_19, 2025/09

https://doi.org/10.1016/j.jhazmat.2025.139031

In this presentation, we analyzed the chemical state of cesium in radiocesium-bearing microparticles (CsMPs) released during the 2011 Fukushima Daiichi Nuclear Power Plant accident using high-resolution X-ray absorption spectroscopy (XANES) and micro X-ray fluorescence (-XRF). The results identified two forms of cesium: one dissolved in glass and the other enriched on the surfaces of internal voids. The latter is considered to have originally existed as a gas and became concentrated during the cooling and solidification of the molten glass. These findings are crucial for understanding the formation process of CsMPs during the accident, as well as for future decommissioning and safety assessments.

Validation study on SFR core bowing codes using Joyo ex-core experiment data; Multiple duct bowing benchmark

Wozniak, N.*; Ohgama, Kazuya; Doda, Norihiro; Ota, Hirokazu*; Shemon, E.*; Feng, B.*; Uwaba, Tomoyuki; Futagami, Satoshi; Tanaka, Masaaki; Yamano, Hidemasa; et al.

Progress in Nuclear Science and Technology (Internet), 8, p.165 - 170, 2025/09

https://doi.org/10.15669/pnst.8.165

To enhance the accuracy of the safety evaluations for sodium-cooled fast reactors, it is necessary to develop a method that can realistically evaluate the reactivity changes induced by core deformation. In this context, Japan and the United States jointly conducted a benchmark analysis of thermal bowing experiments using multiple ducts from a Joyo-type fuel assembly. The aim was to confirm the validity of the core bowing analysis codes. Comparisons of analysis and experimental results demonstrated that the codes used by both countries were able to reasonably predict the thermal bowing of a row of assemblies in multiple duct configuration.

Core deformation reactivity with neutronics-thermal hydraulics-structural mechanics coupled analysis for FFTF LOFWOS Test #13

Doda, Norihiro; Kato, Shinya; Uwaba, Tomoyuki; Tanaka, Masaaki; Nakamine, Yoshiaki*; Igawa, Kenichi*; Iida, Masaki*

Proceedings of 21st International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-21) (Internet), 14 Pages, 2025/08

Accurate evaluation of reactivity feedback due to core deformation during power increases in sodium-cooled fast reactors requires comprehensive modeling of the interactions among neutronics, thermal-hydraulics, and core mechanics. To accurately consider these interactions, JAEA has developed an evaluation method that combines multiple analysis codes that model these phenomena in detail. In this study, the evaluation method was applied to the core analysis of the FFTF LOFWOS Test #13, and the analysis results of net reactivity were compared with the test results. The sensitivity analysis results of the core structural design parameters showed that the core bowing behavior has a significant effect on the temporal variation of net reactivity.

Surface and interfacial aggregation states in thin films of a polystyrene/polyrotaxane blend

Taguchi, Miki*; Miyata, Noboru*; Miyazaki, Tsukasa*; Aoki, Hiroyuki; Ozawa, Satoru*; Hasegawa, Ryuichi*; Morimitsu, Yuma*; Kawaguchi, Daisuke*; Yamamoto, Satoru*; Tanaka, Keiji*

Polymer Journal, 57(7), p.737 - 743, 2025/07

https://doi.org/10.1038/s41428-025-01030-y

Experimental studies on spatial resolution of a delay-line current-biased kinetic inductance detector

Vu, TheDang*; Shishido, Hiroaki*; Aizawa, Kazuya; Oku, Takayuki; Oikawa, Kenichi; Harada, Masahide; Kojima, Kenji M*; Miyajima, Shigeyuki*; Soyama, Kazuhiko; Koyama, Tomio*; et al.

Nuclear Instruments and Methods in Physics Research A, 1075, p.170425_1 - 170425_9, 2025/06

https://doi.org/10.1016/j.nima.2025.170425

Competition between mass-symmetric and asymmetric fission modes in Md produced in the He + Es reaction

Nishio, Katsuhisa; Hirose, Kentaro; Makii, Hiroyuki; Orlandi, R.; Kean, K. R.*; Tsukada, Kazuaki; Toyoshima, Atsushi*; Asai, Masato; Sato, Tetsuya; Chiera, N. M.*; et al.

Physical Review C, 111(4), p.044609_1 - 044609_12, 2025/04

https://doi.org/10.1103/PhysRevC.111.044609

Development of a method for distinguishing alpha particles from other types of radiation using a high-resolution alpha imager

Morishita, Yuki; Sagawa, Naoki; Fujisawa, Makoto; Kurosawa, Shunsuke*; Sasano, Makoto*; Hayashi, Masateru*; Tanaka, Hiroki*

Radiation Measurements, 181, p.107371_1 - 107371_5, 2025/02

https://doi.org/10.1016/j.radmeas.2024.107371

The effects of different types of radiation on a high-resolution alpha imager developed using an electron multiplying charge-coupled device (EMCCD) camera were investigated. This imager was originally developed to visualize alpha particles from Pu oxide particles at decommissioning sites. Other types of radiation such as beta particles, gamma rays, and neutrons are also present. The purpose of this study is to investigate the effects of these background radiations on the imager and to develop a method to discriminate between alpha particles and other types of radiation. When measuring gamma rays, and neutrons, the sensor of the EMCCD camera generated high intensity signals due to gamma rays and neutrons. These radiations were identified by image processing. The image values were binarized and the findContours function was applied to count the number of alpha particle spots. The results showed that alpha and gamma (neutron) radiation can be discriminated by using differences in intensity. This method will be useful for visualizing alpha particles at decommissioning sites.

Developing an online composition prediction for an HI-I-HO system using deep neural network

Tanaka, Nobuyuki; Takegami, Hiroaki; Noguchi, Hiroki; Kamiji, Yu; Myagmarjav, O.; Ono, Masato; Sugimoto, Chihiro

Chemical Engineering Science, 299, p.120479_1 - 120479_11, 2024/11

https://doi.org/10.1016/j.ces.2024.120479

We developed a deep neural network method to predict the composition of the iodine-sulfur process of thermochemical water-splitting hydrogen production using measurable properties. Unlike conventional titration analysis, this approach allows a quick understanding of fluid composition, providing essential information for controlling operating conditions. This study focused on the HI-I-HO three-component system within the IS process. Using Gibbs phase rule, the DNN model was constructed using online measurable parameters, such as temperature, pressure, and density, as input conditions. The model was trained with experimental data, and the structural parameters were tuned. Composition prediction using actual trend data demonstrated good correlation with titration analysis measurements. Furthermore, the local interpretable model-agnostic explanations method was incorporated to gain insights into the significance of input parameters for compositions from the DNN model, providing valuable information on crucial parameters for effective composition control.