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Progress and Status of the Openmc Monte Carlo Code
Free accessDSpace@MIT|Publisher: American Nuclear Society -
Predicting Correlation Coefficients for Monte Carlo Eigenvalue Simulations
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Ocean-Based Passive Decay Heat Removal in the Offshore Floating Nuclear Plant
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Verification of the 3D Method of characteristics solver in OpenMOC
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Using Fractional Cascading to Accelerate Cross Section Lookups in Monte Carlo Neutron Transport Calculations
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
A Cumulative migration method for computing rigorous transport cross sections and diffusion coefficients for LWR lattices with Monte Carlo
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
The Offshore Floating Nuclear Plant Concept
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Quantifying Transient Uncertainty in the BEAVRS Benchmark Using Time Series Analysis Methods
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Reducing 3D MOC Storage Requirements with Axial On-the-fly Ray Tracing
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Theoretical Analysis of Track Generation in 3d Method of Characteristics
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Bayesian Calibration of Safety Codes Using Data from Separate-and Integral Effects Tests
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Simple benchmark for evaluating self-shielding models
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Spatially Continuous Depletion Algorithm for Monte Carlo Simulations
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Design and Fabrication of a DC Feeder System of New TF Magnet Power Supply for Accelerator-Based In-Situ Materials Surveillance in Alcator C-Mod
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Experimental Study of Heat Transfer Mechanisms under Exponential Power Excursion in Plate-Type Fuel
Free accessDSpace@MIT | 2016|Publisher: American Nuclear Society -
Techniques for Stabilizing Coarse-Mesh Finite Difference (CMFD) in Methods of Characteristics (MOC)
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System
Free accessDSpace@MIT | 2014|Publisher: American Nuclear Society -
Direct, on-the-fly calculation of unresolved resonance region cross sections in Monte Carlo simulations
Free accessDSpace@MIT | 2015|Publisher: American Nuclear Society -
Experimental and Analytical Study of Exponential Power Excursion in Plate-Type Fuel
Free accessDSpace@MIT | 2014|Publisher: American Nuclear Society -
Quantitative Phenomena Identification and Ranking Table (QPIRT) for Bayesian Uncertainty Quantification.
Uncertainty Quantification in Safety Codes Using a Bayesian Approach with Data from Separate and Integral Effect TestsFree accessDSpace@MIT | 2012|Publisher: American Nuclear Society
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