Progress in Nuclear Energy
ISSN: 0149-1970
Datasets associated with articles published in Progress in Nuclear Energy
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41 results
- Data for: Profiling and Analysis of Control Rod Speed Design on Core Power Control for TRIGA ReactorThe control rod speed design (CRSD) for core power control has been designed with the actual control rod drive mechanism (CRDM) model by considering the different type of saturations (hard saturation, soft saturation and sigmoid saturation), changes in the maximum control rod speed limiter and reactivity worth curve (experimental data) to predict the best response reactivity insertion rate for operating TRIGA research reactor. The new CRSD (nCRSD) model has been integrated with existing PI-type power controller to study the effects control performance (including small settling time, smoothness control surface during transient, small chattering error during steady-state and actuation signal for CRDM) of the proposed model. The effectiveness of the proposed method is tested by numerical simulations (Matlab/Simulink) and verified with experimental data from real plant by comparing the results with the conventional CRSD (cCRSD based on hard saturation and slow control rod speed).
- Data for: Fission matrix homogenization and other numerical techniques in RAPIDThis data includes the RAPID whole core (BEAVRS benchmark and small core model) transport calculation results with different collapsing options, tolerances of power iterations and precision in floating numbers. It also includes a estimate of the iterative error compared to the real one. Finally, RAPID with all acceleration and numerical techniques are applied on BEAVRS benchmark and compared to Serpent 2 Monte Carlo reference calculation.
- Data for: Advanced Gas-cooled Reactors Technology for Enabling Molten-Salt Reactors Design - Estimation of Coolant Impact on Neutronic PerformanceSerpent input file with BOL and EOL material balance, as was used in the article.
- Data for: Study of the Integrated Falling Liquid Film Model in the Containment Code for Nuclear Safety EvaluationAll the data of the curves in the figures of the article are summarized. All the data of the figures listed in the "docx" file are presented with “opj” files which can be opened with Origin/OriginPro. The original data of each curve can be found with Origin/OriginPro by double clicking the curves and select the “workbook” option.
- Data for: A method for decommissioning strategy proposal and a cost estimation considering a multiple reactor site with interdependent plantsThe file has the data considered for decommissioning cost estimation of the case study site.
- Data for: Numerical Study on Oscillation Characteristics of Large Chugging of Direct Condensation of Steam in a Tee Junction with Flowing Subcooled WaterData for graphs in the manuscript
- Data for: Coupled multi-physics evaluation of an accelerator driven Aqueous Homogeneous Subcritical System for medical isotopes productionData
- Data for: Verification of the Current Coupling Collision Probability Method with Orthogonal Flux Expansion for the Assembly CalculationsResults of calculations for the manuscript "Verification of the Current Coupling Collision Probability Method with Orthogonal Flux Expansion for the Assembly Calculations"
- Data for: Methodology for ultrasonic inspection of dispersion type U-Mo fuel platesUT data and mathematical processing of data
- Data for: Scale effect of amount of molten corium and outlet diameters on corium spreadingThis data file is experimental moving images and raw data obtained by analysis on corium spreading.