Nuclear Engineering and Technology

Papers
(The TQCC of Nuclear Engineering and Technology is 5. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-11-01 to 2024-11-01.)
ArticleCitations
Impact of nuclear and renewable energy sources on environment quality: Testing the EKC and LCC hypotheses for South Korea168
An empirical investigation of nuclear energy consumption and carbon dioxide (CO2) emission in India: Bridging IPAT and EKC hypotheses160
Linking nuclear energy, human development and carbon emission in BRICS region: Do external debt and financial globalization protect the environment?126
Is nuclear energy a better alternative for mitigating CO2 emissions in BRICS countries? An empirical analysis121
The influence of MgO on the radiation protection and mechanical properties of tellurite glasses103
Proposing a gamma radiation based intelligent system for simultaneous analyzing and detecting type and amount of petroleum by-products89
Recent trends of supercritical CO2 Brayton cycle: Bibliometric analysis and research review85
ConvXGB: A new deep learning model for classification problems based on CNN and XGBoost84
Environmental footprint impacts of nuclear energy consumption: The role of environmental technology and globalization in ten largest ecological footprint countries76
The effect of nuclear energy on the environment in the context of globalization: Consumption vs production-based CO2 emissions75
Gamma radiation shielding properties of poly (methyl methacrylate) / Bi2O3 composites70
Dependence assessment in human reliability analysis under uncertain and dynamic situations69
Investigation of photon, neutron and proton shielding features of H3BO3–ZnO–Na2O–BaO glass system69
Investigations on borate glasses within SBC-Bx system for gamma-ray shielding applications68
Evaluating the asymmetric effects of nuclear energy on carbon emissions in Pakistan59
Implementation of waste silicate glass into composition of ordinary cement for radiation shielding applications51
Study on gamma radiation attenuation and non-ionizing shielding effectiveness of niobium-reinforced novel polymer composite50
Nuclear energy consumption and CO2 emissions in India: Evidence from Fourier ARDL bounds test approach47
Determination of true stress-strain curve of type 304 and 316 stainless steels using a typical tensile test and finite element analysis47
Resistance, electron- and laser-beam welding of zirconium alloys for nuclear applications: A review47
Investigating the acceptance of the reopening Bataan nuclear power plant: Integrating protection motivation theory and extended theory of planned behavior44
Effect of surface quality on hydrogen/helium irradiation behavior in tungsten42
Experimental investigation of zinc sodium borate glass systems containing barium oxide for gamma radiation shielding applications42
Testing the pollution haven hypothesis on the pathway of sustainable development: Accounting the role of nuclear energy consumption40
Artificial neural network for predicting nuclear power plant dynamic behaviors40
A novel approach for rice straw agricultural waste utilization: Synthesis of solid aluminosilicate matrices for cesium immobilization39
A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code37
Effect of rare earth dopants on the radiation shielding properties of barium tellurite glasses36
SrAl2Si2O8 ceramic matrices for 90Sr immobilization obtained via spark plasma sintering-reactive synthesis35
A new perspective towards the development of robust data-driven intrusion detection for industrial control systems35
Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth34
Gamma ray exposure buildup factor and shielding features for some binary alloys using MCNP-5 simulation code34
Hydrothermal synthesis, structure and sorption performance to cesium and strontium ions of nanostructured magnetic zeolite composites32
Explore the possible advantages of using thorium-based fuel in a pressurized water reactor (PWR) Part 1: Neutronic analysis31
A comparative study of machine learning methods for automated identification of radioisotopes using NaI gamma-ray spectra30
The optimization for the straight-channel PCHE size for supercritical CO2 Brayton cycle30
Comparative analysis of TiO2, Fe2O3, CaO and CuO in borate based glasses for gamma ray shielding30
Energy optimization of a Sulfur–Iodine thermochemical nuclear hydrogen production cycle29
Revolution of nuclear energy efficiency, economic complexity, air transportation and industrial improvement on environmental footprint cost: A novel dynamic simulation approach29
Bismuth modified gamma radiation shielding properties of titanium vanadium sodium tellurite glasses as a potent transparent radiation-resistant glass applications28
Nuclear energy consumption, nuclear fusion reactors and environmental quality: The case of G7 countries28
Design and analysis of a free-piston stirling engine for space nuclear power reactor28
A study of predicting irradiation-induced transition temperature shift for RPV steels with XGBoost modeling27
Synthesis of barium-doped PVC/Bi2WO6 composites for X-ray radiation shielding27
Review on sodium corrosion evolution of nuclear-grade 316 stainless steel for sodium-cooled fast reactor applications27
Role of A-TIG process in joining of martensitic and austenitic steels for ultra-supercritical power plants -a state of the art review26
Comparison of nano/micro lead, bismuth and tungsten on the gamma shielding properties of the flexible composites against photon in wide energy range (40 keV–662 keV)26
Pore structure evolution characteristics of sandstone uranium ore during acid leaching26
Bentonite based ceramic materials from a perspective of gamma-ray shielding: Preparation, characterization and performance evaluation26
Performance of 3D printed plastic scintillators for gamma-ray detection25
Physical characterization and radiation shielding features of B2O3As2O3 glass ceramic25
A reliable intelligent diagnostic assistant for nuclear power plants using explainable artificial intelligence of GRU-AE, LightGBM and SHAP25
Prediction of critical heat flux for narrow rectangular channels in a steady state condition using machine learning24
Hydrogen production in the light of sustainability: A comparative study on the hydrogen production technologies using the sustainability index assessment method24
Path planning in nuclear facility decommissioning: Research status, challenges, and opportunities24
The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT24
Automated detection of corrosion in used nuclear fuel dry storage canisters using residual neural networks24
Magnesium potassium phosphate cements to immobilize radioactive concrete wastes generated by decommissioning of nuclear power plants24
Mechanical performance of additively manufactured austenitic 316L stainless steel22
Natural radioactivity level in fly ash samples and radiological hazard at the landfill area of the coal-fired power plant complex, Vietnam22
Effect of mechanical alloying on the microstructural evolution of a ferritic ODS steel with (Y–Ti–Al–Zr) addition processed by Spark Plasma Sintering (SPS)22
Fabrication, characterization, simulation and experimental studies of the ordinary concrete reinforced with micro and nano lead oxide particles against gamma radiation22
Determination of energy resolution for a NaI(Tl) detector modeled with FLUKA code21
Modelling of effective irradiation swelling for inert matrix fuels21
FPGA application for wireless monitoring in power plant21
Impacts of the calcination temperature on the structural and radiation shielding properties of the NASICON compound synthesized from zircon minerals20
Design and analysis of isolation effectiveness for three-dimensional base-seismic isolation of nuclear island building20
Research on diagnosis method of centrifugal pump rotor faults based on IPSO-VMD and RVM20
Challenges of implementing the policy and strategy for management of radioactive waste and nuclear spent fuel in Indonesia20
Disturbance observer based adaptive sliding mode control for power tracking of PWRs20
Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model20
Experiment and modeling of liquid-phase flow in a venturi tube using stereoscopic PIV19
The influence of BaO on the mechanical and gamma / fast neutron shielding properties of lead phosphate glasses19
A novel approach for analyzing the nuclear supply chain cyber-attack surface19
Enhancement and optimization of gamma radiation shielding by doped nano HgO into nanoscale bentonite19
A closer look at the structure and gamma-ray shielding properties of newly designed boro -tellurite glasses reinforced by bismuth (III) oxide19
Recent research towards integrated deterministic-probabilistic safety assessment in Korea19
Gamma and neutron shielding properties of B4C particle reinforced Inconel 718 composites19
The Pahlev Reliability Index: A measurement for the resilience of power generation technologies versus climate change19
Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel18
A comprehensive review on clay swelling and illitization of smectite in natural subsurface formations and engineered barrier systems18
Mitigation of seismic responses of actual nuclear piping by a newly developed tuned mass damper device18
Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor18
X-ray / gamma ray radiation shielding properties of α-Bi2O3 synthesized by low temperature solution combustion method18
Evaluation of thermal-hydraulic performance and economics of Printed Circuit Heat Exchanger (PCHE) for recuperators of Sodium-cooled Fast Reactors (SFRs) using CO2 and N2 as working fluids18
Cavitation state identification of centrifugal pump based on CEEMD-DRSN18
Review of researches on coupled system and CFD codes18
Laser decontamination for radioactive contaminated metal surface: A review18
Investigation of thorium separation from rare-earth extraction residue via electrosorption with carbon based electrode toward reducing waste volume17
Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARK17
Fractal kinetic characteristics of uranium leaching from low permeability uranium-bearing sandstone17
Smart grid and nuclear power plant security by integrating cryptographic hardware chip17
Development of hand-held coded-aperture gamma ray imaging system based on GAGG(Ce) scintillator coupled with SiPM array17
Efficiency of various structural modeling schemes on evaluating seismic performance and fragility of APR1400 containment building17
Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters17
Using artificial intelligence to detect human errors in nuclear power plants: A case in operation and maintenance16
Influence of aluminum and vanadium oxides on copper borate glass: A physical/radiological study16
Radiation parameterizations and optical characterizations for glass shielding composed of SLS waste glass and lead-free materials16
Fractional radioactive decay law and Bateman equations16
Imbalanced sample fault diagnosis method for rotating machinery in nuclear power plants based on deep convolutional conditional generative adversarial network16
FPGA integrated IEEE 802.15.4 ZigBee wireless sensor nodes performance for industrial plant monitoring and automation16
Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments16
CFD analysis of the flow blockage in a rectangular fuel assembly of the IAEA 10 MW MTR research reactor16
Evaluation of MCC seismic response according to the frequency contents through the shake table test16
Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor16
A framework of examining the factors affecting public acceptance of nuclear power plant: Case study in Saudi Arabia16
The radiation shielding competence and imaging spectroscopic based studies of Iron ore region of Kozhikode district, Kerala16
Dynamic characteristics of single door electrical cabinet under rocking: Source reconciliation of experimental and numerical findings15
Thermal conductivity prediction model for compacted bentonites considering temperature variations15
Impact of aperture-thickness on the real-time imaging characteristics of coded-aperture gamma cameras15
Machine learning modeling of irradiation embrittlement in low alloy steel of nuclear power plants15
Design of the flexible switching controller for small PWR core power control with the multi-model15
Antecedents of self-reported safety behaviors among commissioning workers in nuclear power plants: The roles of demographics, personality traits and safety attitudes15
Entropy and exergy analysis and optimization of the VVER nuclear power plant with a capacity of 1000 MW using the firefly optimization algorithm15
An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis15
The high thermal stability induced by a synergistic effect of ZrC nanoparticles and Re solution in W matrix in hot rolled tungsten alloy15
Development of a radiological emergency evacuation model using agent-based modeling15
Dynamic reliability analysis framework using fault tree and dynamic Bayesian network: A case study of NPP15
Multi-objective path planning for mobile robot in nuclear accident environment based on improved ant colony optimization with modified A∗15
RNN-based integrated system for real-time sensor fault detection and fault-informed accident diagnosis in nuclear power plant accidents15
A fast high-resolution vibration measurement method based on vision technology for structures15
Study on the neutron imaging detector with high spatial resolution at China spallation neutron source14
Evaluation of photon radiation attenuation and buildup factors for energy absorption and exposure in some soils using EPICS2017 library14
Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS14
Instrumentation and control systems design for nuclear power plant: An interview study with industry practitioners14
Deep neural network based prediction of burst parameters for Zircaloy-4 fuel cladding during loss-of-coolant accident14
Optimal earthquake intensity measures for probabilistic seismic demand models of ARP1400 reactor containment building14
Position error compensation of the multi-purpose overload robot in nuclear power plants14
Bragg-curve simulation of carbon-ion beams for particle-therapy applications: A study with the GEANT4 toolkit14
A comprehensive evaluation of Mg-Ni based alloys radiation shielding features for nuclear protection applications14
Integrated risk assessment method for spent fuel road transportation accident under complex environment14
Radionuclide identification method for NaI low-count gamma-ray spectra using artificial neural network14
Comparison of X-ray computed tomography and magnetic resonance imaging to detect pest-infested fruits: A pilot study14
Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)14
A hardening model considering grain size effect for ion-irradiated polycrystals under nanoindentation14
Growth and characterization of detector-grade CdMnTeSe14
Tailoring the properties of spray deposited V2O5 thin films using swift heavy ion beam irradiation14
Engineering critical assessment of RPV with nozzle corner cracks under pressurized thermal shocks14
Concept of an intelligent operator support system for initial emergency responses in nuclear power plants14
Assessment of natural radionuclides and heavy metals contamination to the environment: Case study of Malaysian unregulated tin-tailing processing industry14
Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis13
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules13
Methodology of seismic-response-correlation-coefficient calculation for seismic probabilistic safety assessment of multi-unit nuclear power plants13
A cavitation performance prediction method for pumps PART1-Proposal and feasibility13
Towards effective indirect radioisotope energy converters with bright and radiation hard scintillators of (Gd,Y)3Al2Ga3O12 family13
Effect of different tungsten compound reinforcements on the electromagnetic radiation shielding properties of neopentyl glycol polyester13
Application of POD reduced-order algorithm on data-driven modeling of rod bundle13
Analysis of steam generator tube rupture accidents for the development of mitigation strategies13
Research on non-uniform pressure pulsation of the diffuser in a nuclear reactor coolant pump13
Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants13
A study on the dynamic characteristics of the secondary loop in nuclear power plant13
Recovery of cesium ions from seawater using a porous silica-based ionic liquid impregnated adsorbent13
The influence of the water ingression and melt eruption model on the MELCOR code prediction of molten corium-concrete interaction in the APR-1400 reactor cavity13
Mechanical and thermodynamic stability, structural, electronics and magnetic properties of new ternary thorium-phosphide silicides ThSixP1-x: First-principles investigation and prospects for clean nuc13
Variational nodal methods for neutron transport: 40 years in review13
Determinants of nuclear power expansion in Indonesia13
New method for dependence assessment in human reliability analysis based on linguistic hesitant fuzzy information13
Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations13
Evaluation of various large-scale energy storage technologies for flexible operation of existing pressurized water reactors12
Disturbance observer-based robust backstepping load-following control for MHTGRs with actuator saturation and disturbances12
Entropy, enthalpy, and gibbs free energy variations of 133Cs via CO2-activated carbon filter and ferric ferrocyanide hybrid composites12
Graph neural network based multiple accident diagnosis in nuclear power plants: Data optimization to represent the system configuration12
Scaling analysis of the pressure suppression containment test facility for the small pressurized water reactor12
Investigation of gamma radiation shielding properties of polyethylene glycol in the energy range from 8.67 to 23.19 keV12
Electron beam scattering device for FLASH preclinical studies with 6-MeV LINAC12
SACADA and HuREX part 2: The use of SACADA and HuREX data to estimate human error probabilities12
Direct-contact heat transfer of single droplets in dispersed flow film boiling: Experiment and model assessment12
Flow blockage analysis for fuel assembly in a lead-based fast reactor12
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment12
Experimental research on the mechanisms of condensation induced water hammer in a natural circulation system12
Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation12
Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation12
Design of a scintillator-based prompt gamma camera for boron-neutron capture therapy: Comparison of SrI2 and GAGG using Monte-Carlo simulation12
Thermal aging effect on fracture toughness of GTAW/SMAW of 316L stainless steel: experiments and applicability of existing CASS models12
An investigation of the nuclear shielding effectiveness of some transparent glasses manufactured from natural quartz doped lead cations12
Validation of RANS models and Large Eddy simulation for predicting crossflow induced by mixing vanes in rod bundle12
Monte Carlo simulations of chromium target under proton irradiation of 17.9, 22.3 MeV12
Does nuclear energy reduce consumption-based carbon emissions: The role of environmental taxes and trade globalization in highest carbon emitting countries12
Temperature-dependent axial mechanical properties of Zircaloy-4 with various hydrogen amounts and hydride orientations12
Unsupervised learning algorithm for signal validation in emergency situations at nuclear power plants12
Design, construction, and characterization of a Prompt Gamma Neutron Activation Analysis (PGNAA) system at Isfahan MNSR11
Optimization of block-matching and 3D filtering (BM3D) algorithm in brain SPECT imaging using fan beam collimator: Phantom study11
Neutron spectroscopy using pure LaCl3 crystal and the dependence of pulse shape discrimination on Ce-doped concentrations11
Dynamic analysis of multi-functional maintenance platform based on Newton-Euler method and improved virtual work principle11
Abnormal state diagnosis model tolerant to noise in plant data11
Fuzzy FMECA analysis of radioactive gas recovery system in the SPES experimental facility11
On the use of flyash-lime-gypsum (FaLG) bricks in the storage facilities for low level nuclear waste11
Experimental and numerical investigation on the pressure pulsation in reactor coolant pumps under different inflow conditions11
Towards a physics-based description of intra-granular helium behaviour in oxide fuel for application in fuel performance codes11
Adsorption and separation behaviors of Y(III) and Sr(II) in acid solution by a porous silica based adsorbent11
Enhanced mechanical properties and interface structure characterization of W–La2O3 alloy designed by an innovative combustion-based approach11
Experimental investigation of two-phase natural circulation loop as passive containment cooling system11
Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K11
Multi-objective optimization of printed circuit heat exchanger with airfoil fins based on the improved PSO-BP neural network and the NSGA-II algorithm11
Investigation of acrylic/boric acid composite gel for neutron attenuation11
Application of STPA-SafeSec for a cyber-attack impact analysis of NPPs with a condensate water system test-bed11
Power peaking factor prediction using ANFIS method11
Validation of spent nuclear fuel decay heat calculation by a two-step method11
Extraction behaviors of platinum group metals in simulated high-level liquid waste by a hydrophobic ionic liquid bearing an amino moiety11
Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor11
A cavitation performance prediction method for pumps: Part2-sensitivity and accuracy11
A multi-layer approach to DN 50 electric valve fault diagnosis using shallow-deep intelligent models11
Application of the machine learning technique for the development of a condensation heat transfer model for a passive containment cooling system11
Synthesis, physical, optical and radiation shielding properties of Barium-Bismuth Oxide Borate-A novel nanomaterial11
Potential of biochar reinforced concrete as neutron shielding material11
Seepage characteristics of the leaching solution during in situ leaching of uranium11
Characterization of Rhizophora SPP. particleboards with SOY protein isolate modified with NaOH/IA-PAE adhesive for use as phantom material at photon energies of 16.59–25.26 keV11
The relationship between public acceptance of nuclear power generation and spent nuclear fuel reuse: Implications for promotion of spent nuclear fuel reuse and public engagement11
Design and evaluation of an innovative LWR fuel combined dual-cooled annular geometry and SiC cladding materials10
The status of NORMs in natural environment adjacent to the Rooppur nuclear power plant of Bangladesh10
Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling10
Development of a prediction model relating the two-phase pressure drop in a moisture separator using an air/water test facility10
Effect of radiation model on simulation of water vapor - hydrogen premixed flame using flamelet combustion model in OpenFOAM10
Evaluation of the radiation damage effect on mechanical properties in Tehran research reactor (TRR) clad10
Numerical analysis of melt migration and solidification behavior in LBR severe accident with MPS method10
Sorption behavior of Eu(Ⅲ) on Tamusu clay under strong ionic strength: Batch experiments and BSE/EDS analysis10
Effects of the move towards Gen IV reactors in capacity expansion planning by total generation cost and environmental impact optimization10
Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics10
Application of deep neural networks for high-dimensional large BWR core neutronics10
Sentiment analysis of nuclear energy-related articles and their comments on a portal site in Rep. of Korea in 2010–201910
Reprocessing of spent nuclear fuel in carbonate media: Problems, achievements, and prospects10
Analysis and optimization research on latch life of control rod drive mechanism based on approximate model10
Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel10
Thermal stability of nitric acid solutions of reducing agents used in spent nuclear fuel reprocessing10
On-site water level measurement method based on wavelength division multiplexing for harsh environments in nuclear power plants10
Anode processes on Pt and ceramic anodes in chloride and oxide-chloride melts10
Application of a deep learning algorithm to Compton imaging of radioactive point sources with a single planar CdTe pixelated detector10
A mechanistic analysis of H2O and CO2 diluent effect on hydrogen flammability limit considering flame extinction mechanism10
Performance evaluation of Accident Tolerant Fuel under station blackout accident in PWR nuclear power plant by improved ISAA code10
Evaluation of 475 °C embrittlement in UNS S32750 super duplex stainless steel using four-point electric conductivity measurements10
Study on the effect of long-term high temperature irradiation on TRISO fuel10
Effects of pulsed laser surface remelting on microstructure, hardness and lead-bismuth corrosion behavior of a ferrite/martensitic steel10
Comparisons of 2-D and 3-D IVR experiments for oxide layer in the three-layer configuration10
Exergetic design and analysis of a nuclear SMR reactor tetrageneration (combined water, heat, power, and chemicals) with designed PCM energy storage and a CO2 gas turbine inner cycle10
Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt10
Effect of thermal aging on the mechanical, intergranular corrosion and corrosion fatigue properties of Z3CN20.09M cast duplex stainless steel10
A review of chloride induced stress corrosion cracking characterization in austenitic stainless steels using acoustic emission technique10
Accumulation and distribution of nutrients, radionuclides and metals by roots, stems and leaves of plants10
Lost gamma source detection algorithm based on convolutional neural network10
The radiation shielding proficiency and hyperspectral-based spatial distribution of lateritic terrain mapping in Irikkur block, Kannur, Kerala9
High-efficiency deep geological repository system for spent nuclear fuel in Korea with optimized decay heat in a disposal canister and increased thermal limit of bentonite9
An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code9
Flow-accelerated corrosion assessment for SA106 and SA335 pipes with elbows and welds9
Convergence analysis of fixed-point iteration with Anderson Acceleration on a simplified neutronics/thermal-hydraulics system9
Role of modifiers on the structural, mechanical, optical and radiation protection attributes of Eu3+ incorporated multi constituent glasses9
Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library9
Research on rapid source term estimation in nuclear accident emergency decision for pressurized water reactor based on Bayesian network9
Possibility of curium as a fuel for VVER-1200 reactor9
The optimum steel fiber reinforcement for prestressed concrete containment under internal pressure9
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis9
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