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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:98.37(Nuclear Science & Technology)

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

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

Kinetic and thermodynamic controls on CsI-Mo gas-phase reactions under varying oxygen potentials

Shiotsu, Hiroyuki

Progress in Nuclear Energy, 195, p.106300_1 - 106300_11, 2026/05

 Times Cited Count:0

Journal Articles

International benchmark on radionuclide solubility and speciation for the Long-term In-situ Test (LIT) at Grimsel Test Site (GTS, Switzerland)

Noseck, U.*; Sch$"a$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

Thermodynamic benchmark calculations have been performed to better understand the behavior of $$^{75}$$Se(VI), $$^{99}$$Tc(VII), $$^{233}$$U(VI), $$^{237}$$Np(V), $$^{241}$$Am(III), Th(IV) and $$^{242}$$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.

Journal Articles

Durability of U-Zr oxide solid solution in aqueous H$$_2$$O$$_2$$ solution

Kumagai, Yuta; Kusaka, Ryoji; Takano, Masahide; Watanabe, Masayuki

Journal of Nuclear Materials, 625, p.156553_1 - 156553_7, 2026/04

 Times Cited Count:0

Uranium-zirconium oxide solid solution, (U, Zr)O$$_2$$, is a representative matrix phase found in fuel debris formed during severe nuclear reactor accidents. Understanding its chemical behavior in oxidative aqueous environments is important for evaluating the potential release of radionuclides during water contact. In this study, we investigated the reactivity of (U, Zr)O$$_2$$ with hydrogen peroxide (H$$_2$$O$$_2$$) in pure water to assess its resistance to oxidative dissolution, because H$$_2$$O$$_2$$ is the dominant oxidant produced by water radiolysis. The dissolution behavior of uranium and zirconium was monitored through repeated H$$_2$$O$$_2$$ exposure experiments, and the solid phases were characterized using Raman micro-spectroscopy and X-ray diffraction. Kinetic modeling was performed to interpret experimental data. The results showed that uranium dissolution occurred initially but decreased significantly upon repeated H$$_2$$O$$_2$$ exposure, while zirconium dissolution proceeded more slowly. Raman analysis revealed only minor surface changes, with limited formation of uranyl peroxide phases. The kinetic simulation reproduced the experimental trends by assuming a small fraction of redox-active surface sites. These findings suggest that the observed durability of (U, Zr)O$$_2$$ against H$$_2$$O$$_2$$-induced oxidative dissolution is not due to the formation of a protective surface layer, but rather reflects the limited redox reactivity of most of the surface. This study provides a quantitative basis for understanding the H$$_2$$O$$_2$$-induced oxidation of (U, Zr)O$$_2$$ in water, relevant to the long-term behavior of fuel debris.

Journal Articles

Highly water-permeable WO$$_{3}$$-containing porous hydrogel via freeze-crosslinking for efficiency and salt-robust dye Decolorization

Sugita, Tsuyoshi; Ueda, Yuki; Nakabe, Rintaro; Mori, Masanobu*; Nankawa, Takuya; Sekine, Yurina

Journal of Photochemistry and Photobiology A; Chemistry, 473, p.116773_1 - 116773_9, 2026/04

 Times Cited Count:0 Percentile:0.00(Chemistry, Physical)

We developed a WO$$_{3}$$-embedded hydrogel (WFG) by freeze-cross-linking that retained high activity even in the presence of coexisting salts. Confocal laser scanning microscope revealed interconnected channels < 200 $$mu$$m. ensuring good water permeability, and contrast-matching small-angle neutron scattering showed that the secondary particle size of embedded WO$$_{3}$$ (~300 nm) matched that in aqueous suspension. Under visible-light irradiation, WFG decolorized indigo carmine (INC) 1.5-fold increase in rate than suspended WO$$_{3}$$ and 3.7-fold increase in rate than a WO$$_{3}$$-coated glass plate. Coexisting salts (NaNO$$_{3}$$, NaCl, Na$$_{2}$$SO$$_{4}$$, NaH$$_{2}$$PO$$_{4}$$) altered the decolorization efficiency; NaNO$$_{3}$$ and Na$$_{2}$$SO$$_{4}$$ enhanced, whereas Cl$$^{-}$$ and H$$_{2}$$PO$$_{4}$$$$^{-}$$ suppressed the reaction, indicating that ionic strength and anion-species affect contact efficiency and charge transfer.

Journal Articles

Reconsideration of numerical model for hydrogen thermal desorption spectra of iron with hydrogen-enhanced strain-induced vacancies

Ebihara, Kenichi; Yamaguchi, Masatake; Itakura, Mitsuhiro

Metallurgical and Materials Transactions A, 57(4), p.1480 - 1489, 2026/04

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.

JAEA Reports

Background aerial monitoring and UAV radiation monitoring technology development for emergency response and preparedness in the fiscal year 2024 (Contract research)

Futemma, Akira; Ochi, Kotaro; Sasaki, Miyuki; Nakama, Shigeo; Kawasaki, Yoshiharu*; Iwai, Takeyuki*; Hiraga, Shogo*; Haginoya, Masashi*; Matsunaga, Yuki*; Sanada, Yukihisa; et al.

JAEA-Technology 2025-015, 171 Pages, 2026/03

JAEA-Technology-2025-015.pdf:11.43MB

On March 11, 2011, the 2011 off the Pacific coast of Tohoku Earthquake and tsunami caused the Fukushima Daiichi Nuclear Power Station accident, releasing radioactive material. Since then, Aerial Radiation Monitoring (ARM) with manned helicopters has been used to assess radiation distribution quickly. In FY2024, the Japan Atomic Energy Agency (JAEA), under commission from the Nuclear Regulation Authority, conducted ARM around the Shimane Nuclear Power Station, producing background dose rate maps validated against ground and other data. During a nuclear emergency drill, UAV training flights complemented manned monitoring, confirming the effectiveness of real-time communication and rapid mapping. The UAV data system was developed and demonstrated for real-time analysis and multi-platform use. Skill training for multicopters was also conducted to strengthen operational capability. Additionally, joint monitoring with the U.S., France, South Korea, and Canada provided insights into international technologies and practices, emphasizing the value of information sharing. This report summarizes the results and technical challenges from these FY2024 activities, contributing to the advancement of emergency radiation monitoring.

JAEA Reports

Annual report of Nuclear Science Research Institute, JFY 2024

Nuclear Science Research Institute

JAEA-Review 2025-061, 183 Pages, 2026/03

JAEA-Review-2025-061.pdf:4.01MB

Nuclear Science Research Institute (NSRI) was composed of Planning and Management Department and six departments, namely Department of Operational Safety Administration, Department of Radiation Protection, Engineering Services Department, Department of Research Reactor and Tandem Accelerator, Department of Criticality and Hot Examination Technology, and Department of Decommissioning and Waste Management, and each department manages facilities and develops related technologies to achieve the "Medium- to Long-term Plan" successfully and effectively. On November 1, NSRI unified Department of Research Reactor and Tandem Accelerator, and Department of Criticality and Hot Examination Technology, newly organized Department of Research Infrastructure Technology Development. And, Planning and Management Department was reorganized to Promotion Office. Continuously, four research centers which are Advanced Science Research Center, Nuclear Science and Engineering Center, Nuclear Engineering Research Collaboration Center and Materials Sciences Research Center, belong to NSRI. In order to contribute to future research and development, and to promote management business, this annual report summarizes information on the activities of NSRI of JFY 2024 as well as the activity on research and development carried out by Collaborative Laboratories for Advanced Decommissioning Science, Nuclear Safety Research Center and activities of Nuclear Human Resource Development Center, using facilities of NSRI.

JAEA Reports

Synthesis report on the R&D for the Horonobe Underground Research Laboratory Project carried out between fiscal years 2020-2024

Nakayama, Masashi; Ishii, Eiichi; Aoyagi, Kazuhei; Hayano, Akira; Ono, Hirokazu; Ozaki, Yusuke; Mochizuki, Akihito; Takeda, Masaki; Kimura, Shun

JAEA-Research 2025-016, 141 Pages, 2026/03

JAEA-Research-2025-016.pdf:13.37MB

The Horonobe Underground Research Laboratory (URL) Project is being pursued by the Japan Atomic Energy Agency (JAEA). The main aim of the project is to enhance the reliability of relevant technologies for the geological disposal of high-level radioactive waste by investigating the deep geological environment within the host sedimentary rocks at Horonobe in Hokkaido, northern Japan. These investigations have been conducted in three phases: "Phase 1: Surface-based investigation", "Phase 2: Construction" (investigation during tunnel excavation) and "Phase 3: Operation" (investigation in subsurface facilities). Since the fiscal year 2020, we have been conducting R&D based on the Horonobe Underground Research Plan for the Fiscal Year 2020 Onwards, which was approved by Hokkaido Prefecture and Horonobe Town. In particular, we are working on the following key tasks with the aim of completing JAEA's 3rd and 4th Mid- and Long-Term Plans: "Study on near-field system performance in geological environments", "Demonstration of repository design options" and "Understanding of buffering behaviour of sedimentary rocks to natural perturbations". This report summarizes the R&D activities on the three above-mentioned key tasks, the goals of which were achieved between fiscal years 2020 and 2024. The results obtained from these tasks will be systematically organized as part of the "Systematic integration of technologies towards EBS emplacement" which has been in progress since fiscal year 2024. This task includes concepts related to the layout of galleries and pits, installation methods for engineered barrier materials, and methods for evaluating their containment performance.

JAEA Reports

Conceptual design of pilot ADS

Nishihara, Kenji; Fukushima, Masahiro; Abe, Takumi; Katano, Ryota; Yee-Rendon, B.; Iwamoto, Hiroki; Sugawara, Takanori; Obayashi, Hironari; Saito, Shigeru

JAEA-Research 2025-013, 125 Pages, 2026/03

JAEA-Research-2025-013.pdf:4.68MB

A conceptual design for a pilot Accelerator Driven subcritical System (ADS) was developed as a precursor to a commercial ADS aimed at partitioning and transmutation of minor actinides. The output of the pilot ADS was set at 200 MW. Based on safety assessment results, the design incorporates deep subcriticality and safety rods. Core design, accelerator design, target design, and in-vessel equipment design were performed, clarifying the specific concept.

Journal Articles

In situ study of growth mechanism of germanene segregated through Ag(111) thin films by Raman and X-ray photoelectron spectroscopy

Terasawa, Tomoo; Katsube, Daiki*; Yano, Masahiro; Ozawa, Takahiro*; Tsuda, Yasutaka; Yoshigoe, Akitaka; Asaoka, Hidehito; Suzuki, Seiya

Chemistry of Materials, 38(6), p.2933 - 2945, 2026/03

AA2025-0822.pdf:1.33MB

 Times Cited Count:0

Journal Articles

Temperature effect on radiolytically generated hydrogen yield from a plutonium nitric acid aqueous solution

Toigawa, Tomohiro; Hotoku, Shinobu; Kumagai, Yuta; Abe, Yuma*; Oyama, Kanichi*; Fukaya, Hiroyuki; Ban, Yasutoshi; Kida, Takashi; Hasegawa, Satoshi*; Nakano, Masanao*; et al.

Journal of Nuclear Science and Technology, 63(3), p.322 - 327, 2026/03

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

The effect of temperature on hydrogen production generated from radiolysis was investigated to determine the associated implications for nuclear fuel reprocessing safety. The hydrogen yield from radiolysis of plutonium nitric acid solution was measured at temperatures up to the boiling temperature of the solution. The results showed no notable temperature dependence even under boiling conditions. The impact of solution agitation on hydrogen production was also assessed, which revealed minor differences in the hydrogen yield between static and agitated conditions at room temperature. These findings suggest that high temperatures or boiling the solution do not considerably enhance hydrogen generation, and provide crucial information for accurately modeling hydrogen risks under severe accidents.

Journal Articles

Operation status of the charge exchange foil and replacement work of the foil transfer mechanism in the J-PARC 3GeV synchrotron

Nakanoya, Takamitsu; Yoshimoto, Masahiro; Saha, P. K.; Takeda, Osamu*; Saeki, Riuji*; Muto, Masayoshi*; Miyo, Takuya*

Proceedings of 22nd Annual Meeting of Particle Accelerator Society of Japan (Internet), p.790 - 794, 2026/03

The J-PARC 3 GeV Rapid Cycling Synchrotron (RCS) utilizes pure carbon foils produced in-house by JAEA as charge exchange foils. In November 2023, during beam commissioning just before the start of user operation, a malfunction occurred in a foil drive mechanism. The foil drive mechanism is responsible for replacing and inserting foils into the beamline. This malfunction prevented remote replacement of the foils. Therefore, when foil replacement was necessary, it was performed manually with visual confirmation near the mechanism. The foil drive mechanism was subsequently replaced and restored during the 2024 summer maintenance period. Despite the issue with the foil drive mechanism, the charge exchange foils demonstrated stability under beam irradiation, and there were no operational problems. Recent efforts have significantly enhanced the durability of the foils against beam irradiation through the implementation of two novel methods. One method involves selecting an appropriate diameter for the carbon rod used in charge exchange foil fabrication. The other method utilizes carbon nanotube (CNT) wire as a support material for the foils. While beam irradiation causes foil deformation, these methods show significantly reduced deformation compared to previous foils. This improvement raises the possibility of using foils for a longer operational lifespan. In this paper, we report on the foil drive mechanism malfunction, subsequent replacement work, and the performance of the charge exchange foils during user operation from 2023 to 2025.

Journal Articles

Pulse bending magnet and septum magnet for 3-GeV proton beam transport line

Yamaguchi, Yuji; Kondo, Yasuhiro; Meigo, Shinichiro; Takayanagi, Tomohiro; Fujimori, Hiroshi*; Shinozaki, Shinichi

Proceedings of 22nd Annual Meeting of Particle Accelerator Society of Japan (Internet), p.655 - 660, 2026/03

Preliminary designs of new bending magnets have been considered for the second target station (TS2) of Materials and Life Science Experimental Facility (MLF), J-PARC. To give a design approach for the bending magnets, several examples of bending magnets, such as a pulse bending magnet and a septum magnet were reviewed. The reviewed magnet specifications compared with requirements for the new bending magnets indicate that the new pulse bending magnet requires a new design idea, while the new septum magnet can be designed based on the previous design of an extraction septum magnet for the 3-GeV synchrotron in J-PARC. The new design idea for the pulse bending magnet and the septum magnet design idea based on the previous one are presented.

Journal Articles

Effect of coaxial HPGe detector structure on $$gamma$$-ray beam measurements

Omer, M.; Shizuma, Toshiyuki*; Koizumi, Mitsuo; Taira, Yoshitaka*; Zen, H.*; Ogaki, Hideaki*; Hajima, Ryoichi*

Radiation Physics and Chemistry, 240, p.113467_1 - 113467_8, 2026/03

 Times Cited Count:0 Percentile:0.00(Chemistry, Physical)

Journal Articles

Stress and temperature, rather than hydrogen, govern stacking fault evolution during tensile deformation in Fe-24Cr-19Ni steel

Ito, Tatsuya; Ogawa, Yuhei*; Gong, W.; Kawasaki, Takuro; Shibata, Akinobu*; Harjo, S.

Scripta Materialia, 273, p.117084_1 - 117084_6, 2026/03

 Times Cited Count:0 Percentile:0.00(Nanoscience & Nanotechnology)

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2024)

Department of HTTR

JAEA-Review 2025-053, 86 Pages, 2026/02

JAEA-Review-2025-053.pdf:3.06MB

This report summarizes the activities carried out in the fiscal year 2024 about the operation and maintenance of the High Temperature Engineering Test Reactor (HTTR), the R&Ds using the HTTR and so on. The HTTR is the first Japanese test reactor of High Temperature Gas-cooled Reactor (HTGR) type with 30MW in thermal power and whose maximum outlet coolant temperature achieved 950$$^{circ}$$C. HTGRs are regarded as the promising candidates of the Next Generation Nuclear Plants conformed to the future decarbonized society because of the inherent safety characteristics as well as high temperature heat supply capability for not only power generation but for wide-ranging industrial uses such as hydrogen production and so on. The HTTR achieved its reactor outlet coolant temperature of 950$$^{circ}$$C under full thermal power of 30MW on April 19, 2004. And since then, HTTR has had a lot of experience of HTGRs' operation and maintenance throughout rated power operations, safety demonstration tests, long-term high temperature operations and demonstration tests relevant to HTGRs' R&Ds. In the fiscal year 2024, we conducted heat load variation tests simulating heat load fluctuations due to equipment abnormalities at thermal utilization facilities (hydrogen production facilities) planned to be connected to HTTR, as well as radioactive iodine quantitative evaluation tests to assess the amount of radioactive iodine deposited in the pipes, assuming a primary double-pipe high temperature gas duct rupture accident of the HTGR. Additionally, to confirm hydrogen production technology using the high-temperature gas reactor, we applied to Nuclear Regulation Authority for a reactor installation change permit to connect a hydrogen production facility to HTTR.

Journal Articles

Ambient dose rate variation in the Fukushima region visualized using explainable AI techniques

Yoshida, Ryu*; Kurikami, Hiroshi; Nagao, Fumiya; Takahashi, Shigeo*; Sanada, Yukihisa

Journal of Environmental Radioactivity, 293, p.107900_1 - 10790_13, 2026/02

 Times Cited Count:0 Percentile:0.00(Environmental Sciences)

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