Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 58659

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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

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

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

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

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

Interpretation of lanthanoid oxide and hydroxide solubilities based on their bulk and surface properties

Kobayashi, Taishi*; Moniruzzaman, M.*; Motokawa, Ryuhei; Sasaki, Takayuki*

Applied Geochemistry, 202, p.106780_1 - 106780_11, 2026/05

 Times Cited Count:0

Journal Articles

Soin-contrast-variation neutron scattering; Innovation in structural analysis

Kumada, Takayuki

Hamon, 36(2), p.62 - 65, 2026/05

no abstracts in English

Journal Articles

Quantitative evaluation of confined water distribution in ionomers within catalyst layers of fuel cells

Iwase, Hiroki*; Arima-Osonoi, Hiroshi*; Harada, Masashi*; Kumada, Takayuki

Hamon, 36(2), p.84 - 88, 2026/05

no abstracts in English

Journal Articles

Model-based development of pulsed electromagnets for accelerators by simulation

Takayanagi, Tomohiro; Ueno, Tomoaki*; Horino, Koki*; Sugita, Moe; Fuwa, Yasuhiro; Shinozaki, Shinichi

IEEE Transactions on Applied Superconductivity, 36(3), p.4900905_1 - 4900905_5, 2026/05

 Times Cited Count:0 Percentile:0.00(Engineering, Electrical & Electronic)

Journal Articles

Chemical kinetic uncertainty quantification for Reynolds-Averaged Navier-Stokes simulations of turbulent premixed combustion

Motegi, Kosuke; Shiotsu, Hiroyuki; Matsumoto, Toshinori; Hibiki, Takashi*; Shibamoto, Yasuteru

International Journal of Heat and Mass Transfer, 258, p.128275_1 - 128275_15, 2026/05

 Times Cited Count:0 Percentile:0.00(Thermodynamics)

Journal Articles

Negative magnetization phenomenon in TbNiC$$_{2}$$

Yamamoto, Masataka*; Hidaka, Hiroyuki*; Yanagisawa, Tatsuya*; Tabata, Chihiro; Nakao, Hironori*; Shimomura, Susumu*; Onodera, Hideya*; Amitsuka, Hiroshi*

Journal of the Physical Society of Japan, 95, p.053703_1 - 053703_4, 2026/05

Journal Articles

Development of quick neutron spectrum reconstruction module based on POD for burnup calculation of fast reactor

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

Journal Articles

A Method for estimating light quenching in inorganic scintillator detectors for radioactive ion beam experiments

Kreinder, B.; Cox, I.*; Grzywacz, R.*; Nishio, Katsuhisa; 24 of others*

Nuclear Instruments and Methods in Physics Research A, 1085, p.171298_1 - 171298_7, 2026/05

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

Journal Articles

Design of a storage ring based on a fixed-field alternating-gradient configuration with an internal target for heavy-ion beams with stochastic charge state conversions

Ishi, Yoshihiro*; Uesugi, Tomonori*; Mori, Yoshiharu*; Nishio, Katsuhisa

Physical Review Accelerators and Beams (Internet), 29(5), p.050101_1 - 050101_14, 2026/05

Journal Articles

Magnetization process of the layered diluted ferromagnetic semiconductor (Ba,K)(Zn,Mn)$$_2$$As$$_2$$ studied by X-ray magnetic circular dichroism

Wan, Y.*; Shibata, Goro; Takeda, Yukiharu*; Okane, Tetsuo; Saito, Yuji; Yamagami, Hiroshi; Fujimori, Atsushi*; 10 of others*

Physical Review Materials (Internet), 10(5), p.054402_1 - 054402_8, 2026/05

58659 (Records 1-20 displayed on this page)