Nuclear Engineering and Design

# The Latest Mendeley Data Datasets for Nuclear Engineering and Design

Mendeley Data Repository is free-to-use and open access. It enables you to deposit any research data (including raw and processed data, video, code, software, algorithms, protocols, and methods) associated with your research manuscript. Your datasets will also be searchable on Mendeley Data Search, which includes nearly 11 million indexed datasets. For more information, visit Mendeley Data.

- The path for immobilizing low-activity waste (LAW), a mixture of salts, for long-term storage is adding glass-forming and modifying additives and minerals to the solution and vitrifying the resulting slurry in an electric melter. Technetium-99 (99Tc), a long-lived radionuclide present in LAW, is highly volatile at the elevated temperatures in a glass melt. An off-gas system was designed for capturing volatile 99Tc or Re, its nonradioactive surrogate, during continuous charging of a LAW melter feed in a laboratory-scale melter (LSM). The Re retention in the glass was determined via the measured amount of volatilized Re in the off-gas during a time period when the reacting melter feed was at a quasi-steady-state. This study was performed in preparation for the LSM system to be applied for melter feeds containing either a LAW simulant spiked with 99Tc or an actual tank waste.
## Data for: Experimental Correlation for Critical Heat Flux in Helical Coils

Experimental data for critical heat flux## Data for: Three dimensional transient analysis of the coupled RCS-containment integral system

Three dimensional transient analysis of the coupled RCS-containment integral system## Data for: Single-Phase, Natural Circulation Annular Flow Measurements for Cartridge Loop Irradiation Experiments

These files provide the raw data from steady-state and transient thermal hydraulic experiments performed as described in the manuscript titled "Single-Phase, Natural Circulation Annular Flow Measurements for Cartridge Loop Irradiation Experiments" submitted to the Nuclear Engineering and Design journal in August 2020.## Data for: RADIATIVE HEAT TRANSFER IN FLIBE MOLTEN SALT PARTICIPATING MEDIUM IN A VERTICAL HEATED TUBE UNDER FORCED AND MIXED CONVECTION LAMINAR FLOWS

The contribution of radiative heat transfer (RHT) to convective heat transfer in a heated vertical pipe with laminar flow and constant wall temperature, for FLiBe molten salt, is investigated computationally. The combined effects of conduction in the fluid, forced convection, buoyancy, temperature-dependent physical properties, and thermal radiation are investigated. The P1 approximation is employed in the discretization of the Radiative Transfer Equation (RTE). The COMSOL Multiphysics software is used to generate the numerical solutions. Theoretical analysis demonstrates that only for intermediate values of the optical thickness, i.e. τ_D~O(1), the participating media effects are expected to be important. This analysis is confirmed computationally, where a value of τ_D≈4 is shown to lead to the highest increase in overall heat transfer behavior. Under forced convection, the Nusselt ratio Nu_total/ Nu_(no-rad) reaches a peak value of 1.76 at τ_D=4 and z/D=200, and is less than 1.1 for τ_D60. Under aiding-flow mixed convection, Nu_total/ Nu_(no-rad) reaches a peak of 1.34 at τ_D=4.2 and is less than 1.1 for τ_D36. Under opposing-flow mixed convection, Nu_total/ Nu_(no-rad) reaches a peak of 1.81 at τ_D=4.2 and is less than 1.1 for τ_D50. RHT effects on the overall heat transfer are most pronounced in opposing mixed convection where peak Nu_total/ Nu_(no-rad) is 2.26 observed at z/D=50. The sensitivity to wall emissivity is evaluated; in forced convection, the peak Nu_total/ Nu_(no-rad) is 1.66 at ε=0 (reflective wall) and 2.04 at ε=1 (absorptive wall). The sensitivity to pipe diameter is also discussed. Overall, for a vertical heated tube, radiative heat transfer effects lead to enhancement of heat transfer by as high as a factor of two, and they depend on the optical thickness of the flow, mixed convection environment (Gr\/Re^2 and direction of flow relative to the gravitational force), surface emissivity, and entrance effects.## Data for: Designs of Control Rods with Strong Absorption Ability for Small Fast Reactors

The properties of boron carbide, hafnium diboride, and hafnium hydride.## Data for: A Unique Molten Salt Reactor Feature - The Freeze Valve System: Design, Operating Experience, and Reliability

Fault trees for 2 failure modes of MSRE freeze valve FV-103 and supporting basic event data## Data for: Lead-Bismuth Eutectic (LBE) Expansion Behavior with Heat Treatment

Measured data of each sample. CSV files named as 5Kmin, 15Kmin, 05Kmin, and 0125Kmin indicates the samples cooled at 5, 3/2, 1/2, and 1/8 Kmin-1, respectively.## Data for: Extension and Preliminary Validation of the Polaris Lattice Physics Code for CANDU Analysis

Contains input files (both complete input files as well as templates) along with some output files and CSV-formatted results, along with a few additional figures. Some of the results are not directly used in the corresponding publication, and are either indirectly used, or correspond to cases that were not included in the paper at all; usually those similar to the cases used in the paper, but with different parameters. The Polaris input files are incompatible with the distributed version of SCALE 6.2.## Data for: Validation of Pronghorn Friction-Dominated Porous Media Thermal-Hydraulics Model with the SANA Experiments

This is a Python script containing all of the Pronghorn simulation results at the thermocouple locations. The data is stored in dictionaries, with various levels of "indentation" to contain all of the variations in closure model selection. This script plots the histograms included in the article.## Data for: A best-estimated correlation for prediction of nucleation superheat in sodium-cooled fast reactor

Raw data of Fig.4-Fig.6## Data for: SECOND-ORDER SENSITIVITIES OF A GENERAL FUNCTIONAL OF THE FORWARD AND ADJOINT FLUXES IN A MULTIPLYING NUCLEAR SYSTEM WITH SOURCE

• This work presents an application of the Second-Order Adjoint Sensitivity Analysis Methodology (2nd-ASAM) • The number of computations within the 2nd-ASAM to obtain the 1st- and 2nd-order response sensitivities to model parameters increases linearly in augmented Hilbert spaces as opposed to increasing exponentially in the original Hilbert space. • Therefore, the 2nd-ASAM computes exactly all of the 1st- and 2nd-order responses sensitivities to model parameters with unmatched efficiency. • The system response considered is a nonlinear functional of the forward and adjoint particle fluxes in a multiplying subcritical system comprising a non-fission neutron source, while the system parameters include isotopic number densities, microscopic cross sections, fission spectrum, sources, and detector response functions.## Data for: Experimental tests and post-test analysis of non-uniformly heated 19-pins fuel bundle cooled by Heavy Liquid Metal

The two .txt files (ADP_06 and ADP_07) contain the raw experimental data. TC nomenclature.docx file contains the nomenclature and location of the termocouples inside the Fuel Pin bundle simulator (test section). The other files contains the matlab scripts adopted for post-processing the raw data files.## Data for: Numerical Study on reverse flow in U-tubes of UTSG under Natural Circulation

This paper is to set up the computational fluid dynamics model, compared with estimate code RELAP5/MOD3.3, to study the different phenomenons of reverse flow in the inclined and vertical UTSG under natural circulation condition. The methods and the typical results are shown in the research data.## Data for: Modeling Heat Transfer through Corrosion Product Deposits on Fuel Rods in Pressurized Water Reactors

Matlab script for the analysis using the current model.## Data for: Modeling Crust Fracture and Water ingression through Crust during Top-flooding strategy for Corium Cooling

Results calculated from the present model and the data used for comparison## Data for: Simulations of advanced reactor cores in experimental light water reactor LR-0

Calculated and measured neutron spectra for LR-0 reactor and advanced types of reactors.## Data for: Simulated Time-Dependent Data to Estimate Uncertainty in Fluid Flow Measurements

The reconstructed and prescribed positions for verification of Positron Emission Particle Tracking algorithm are compared to identify novel reconstruction errors experienced in multi PEPT measurements. The reconstructed tracer number 421 initially follows prescribed tracer 560. Later the reconstruction incorporates a position from the prescribed tracer number 559, switching to this tracer for the remainder of its trajectory.## Functional Expansion (FE) Algorithm Optimization - Benchmarking Data

This data contains the effective computation time of different algorithms for evaluating terms in orthogonal polynomials series. Algorithms for the Legendre and Zernike polynomial series were evaluated. The underlying algorithms are described in an submitted journal article that is currently under review. The "answer" value of the data set has no external use. Instead, it was an accumulated value that was used throughout the benchmarking process to prevent over-aggressive compiler optimizations from removing the loops used for benchmarking. Conveniently, it provided a way to debug and validate the algorithm variations by comparison with each other. The source files were updated from v1 to correct errors in Zernike polynomials for $Z_7^{\pm3}$. These were propagated from: V. Lakshminarayanan and A. Fleck. Zernike polynomials: a guide [http://dx.doi.org/10.1080/09500340.2011.633763] The value '2' should be replaced by '21'.