| Features of Particle and Heavy Ion Transport code System (PHITS) version 3.02 |
123 |
| The pseudo-resonant-nuclide subgroup method based global-local self-shielding calculation scheme |
10 |
| Remote radiation imaging systemusing a compact gamma-ray imager mounted on amulticopter drone |
10 |
| Radiation imaging using a compact Compton camera mounted on a crawler robot inside reactor buildings of Fukushima Daiichi Nuclear Power Station |
6 |
| Features of a control blade degradation observed in situ during severe accidents in boiling water reactors |
5 |
| Experimental analysis and uncertainty quantification using random sampling technique for ADS experiments at KUCA |
5 |
| Fukushima Daiichi fuel debris simulant materials for the development ofcutting and collection technologies |
5 |
| Removal of uranium(VI) from aqueous solution using graphene oxide functionalized with diethylenetriaminepentaacetic phenylenediamine |
5 |
| Oxidation behavior of high-burnup advanced fuel cladding tubes in high-temperature steam |
5 |
| Reaction rate analyses of accelerator-driven system experiments with 100 MeV protons at Kyoto University Critical Assembly |
5 |
| Application of InGaP space solar cells for a radiation dosimetry at high dose rates environment of Fukushima Daiichi nuclear power plant |
4 |
| Thermal and mechanical properties of polycrystalline U3Si2 synthesized by spark plasma sintering |
4 |
| Ultra-fine-group resonance treatment using equivalent Dancoff-factor cell model in lattice physics code GALAXY |
4 |
| Sensitivity analysis of prompt neutron decay constant using perturbation theory |
4 |
| Research activities on nuclear reactor physics and thermal-hydraulics in Japan after Fukushima-Daiichi accident |
4 |
| Verification and validation of explicit moving particle simulation method for application to internal flooding analysis in nuclear reactor building |
4 |
| An experimental investigation of influencing chemical factors onCs-chemisorption behavior onto stainless steel |
4 |
| Model updates and performance evaluations on fuel performance code FEMAXI-8 for light water reactor fuel analysis |
3 |
| Estimation of time-dependent neutron transport from point source based on Monte Carlo power iteration |
3 |
| The effect of hydride morphology on the failure strain of stress-relieved Zircaloy-4 cladding with an outer surface pre-crack under biaxial stress states |
3 |
| Development of a treatment process and immobilization method for the volume reduction of uranium-bearing spent catalysts for final disposal |
3 |
| A summary of the 'ALARP' principle and associated thinking |
3 |
| Chemical reaction kinetics dataset of Cs-I-B-Mo-O-H system for evaluation of fission product chemistry under LWR severe accident conditions |
3 |
| Sedimentation behavior of mixed solid particles |
3 |
| First nuclear transmutation of Np-237 and Am-241 by accelerator-driven system at Kyoto University Critical Assembly |
3 |
| Experimental study of neutron counting in a zero-power reactor driven by a neutron source inherent in highly enriched uranium fuels |
3 |
| Thermal hydraulic analysis of supercritical water reactor cooled by TiO2 nanofluid |
3 |
| Development of an all-sky gamma-ray Compton camera based on scintillators for high-dose environments |
3 |
| An impact of inherent neutron source on subcriticality measurement in a highly enriched uranium core of Kyoto University Critical Assembly |
3 |
| U-235(n, f) Independent fission product yield and isomeric ratio calculated with the statistical Hauser-Feshbach theory |
3 |
| Radiation imaging using a compact Compton camera inside the Fukushima Daiichi Nuclear Power Station building |
3 |
| A review of revaporisation behaviour of radioactive Cs deposits and its impact on the source term in severe nuclear accidents from Phebus FP results and single effect testing |
3 |
| Control rod position measurement by two-electrode capacitance sensor in nuclear heating reactor |
3 |
| Deformation behavior of recrystallized and stress-relieved Zircaloy-4 fuel cladding under biaxial stress conditions |
2 |
| Calculation of gamma and neutron emission characteristics emitted from fuel debris of Fukushima Daiichi Nuclear Power Station |
2 |
| An intranuclear cascade model for inelastic scattering and breakup reactions involving deuterons and alpha particles |
2 |
| Seismic analysis of nuclear power plants by using three-dimensional finite element models: a review |
2 |
| A hybrid method to generate few-group cross sections for fast reactor analysis |
2 |
| Effect of quenching on molten core-concrete interaction product |
2 |
| Development of a stochastic biokinetic method and its application to internal dose estimation for insoluble cesium-bearing particles |
2 |
| Generalized formulation of extended cross-section adjustment method based on minimum variance unbiased linear estimation |
2 |
| Neutronics analysis of megawatt-class gas-cooled space nuclear reactor design |
2 |
| Behavior of cesium molybdate, Cs2MoO in severe accident conditions. (1) Partitioning of Cs and Mo among gaseous species |
2 |
| Synthesis of amidoxime polymer gel to extract uranium compound from seawater by UV radiation curing |
2 |
| Comparison of pool boiling CHF of a polished copper block and carbon steel block on a declined slope |
2 |
| Application of various observational techniques to the characterization of MX in F82H |
2 |
| Measurements of thermal-neutron capture cross-section and resonance integral of neptunium-237 |
2 |
| Measurements of neutron total and capture cross sections of Am-241 with ANNRI at J-PARC |
2 |
| Uncertainty quantification of criticality in solid-moderated and -reflected cores at Kyoto University Critical Assembly |
2 |
| Proposal of an insider sabotage detection method for nuclear security using deep learning |
2 |
