Nuclear Engineering and Technology
ISSN: 1738-5733
Datasets associated with articles published in Nuclear Engineering and Technology
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16 results
- Data for: Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locationsAn extensive single clad tube burst test on pre-hydrided Zircaloy-4 cladding using direct electrical heating in inert environment
- Data for: Analysis of VVER-1000 Mock-up Criticality Experiments with Nuclear Data Library ENDF/B-VIII.0 and Monte Carlo code MCSThis research data contains 12 inputs: 6 for the Monte Carlo code MCNP (developed at Los Alamos, New Mexico) and 6 for the Monte Carlo code MCS (developed at UNIST, South Korea). For each code, the inputs are criticality calculations modelling 6 different critical configurations of the VVER-1000 mock-up. All the inputs correspond to the reference calculations without sensivity analysis / perturbations (all the values of parameters are nominal). All the inputs use the ENDF/B-VII.1 library. The inputs are included as supplementary material with the hope that they are useful for the interpretation of VVER-1000 mock-up benchmarks, but without any warranty.
- Data for: Deep neural network based prediction of burst parameters for Zircaloy-4 fuel cladding during loss-of-coolant accidentThis is database of single-tube burst tests conducted on unirradiated Zircaloy-4 cladding tubes under simulated loss-of-coolant transients. This database was used for developing Deep neural network model to prediction burst parameters for Zircaloy-4 fuel cladding during loss-of-coolant accident.
- Data for: Effect of Octadecylamine Concentration on Adsorption on Carbon Steel SurfaceFilm firming study.
- Data for: Gamma Spectrum Denoising Method Based on Improved Wavelet ThresholdData used in this paper
- Data for: Application of Cost-Sensitive LSTM in Water Level Prediction for Nuclear Reactor Pressurizerdata: Normalized data sampled from a nuclear power plant simulator, including pressurizer water level and other six parameters according to the transient process of increasing reactor power from 30% to 90%. code: including CSLSTM, LSTM and SVR models in two experiment settings, i.e. global learning setting and local learning setting.
- Data for: Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCSThis research data contains 20 inputs: 10 for the Monte Carlo code MCNP (developed at Los Alamos, New Mexico) and 10 for the Monte Carlo code MCS (developed at UNIST, South Korea). The inputs correspond to 10 shielding problems modelling the benchmarks NEA-1517/74 and NEA-1517/80 from the SINBAD (Shielding Integral Benchmark Archive and Database) shielding database. The inputs are provided in the hope that they are useful for the interpretation of the benchmark measurements performed in the Russian Federal Nuclear Center (RFNC) of photon leakage from hollow spherical samples with a central 14-MeV neutron source produced by deutrium-tritium fusion, but without any warranty. The 10 material samples used in the measurements and modeled in the inputs are: aluminum, titanium, iron, copper, zirconium, lead, depleted uranium, water, salt and sand.
- Data for: DOSE COEFFICIENTS OF MESH-TYPE ICRP REFERENCE COMPUTATIONAL PHANTOMS FOR EXTERNAL EXPOSURES OF NEUTRONS, PROTONS, AND HELIUM IONSA comprehensive set of dose coefficients for external exposures of neutrons, protons, and helium ions, which were produced by conducing Monte Carlo particle transport simulations with the adult male and female mesh-type ICRP reference computational phantoms
- Data for: Bilateral comparison of the absorbed dose to water in high energy X-ray beams between the KRISS and the NMIJThe data sets are (1) the technical protocol prepared for the comparison study and (2) the results reported by the KRISS.
- Data for: Acceleration Method of Fission Source Convergence Based on RMC code relavant materials for the paper submitted to NET - calculation results.