publication venue for
- Traditional machine learning methods in predicting the physics of subcritical systems in source-equilibrium. 201:110413-110413. 2024
- CFD assessment of RANS turbulence modeling for solidification in internal flows against experiments and higher fidelity LBM-LES phase change model. 197:110275-110275. 2024
- On the need for multi-dimensional models for the safety analysis of (fast-spectrum) Molten Salt Reactors. 197:110237-110237. 2024
- Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark. 194:110092-110092. 2023
- Numerical study of the impact of blockages on the Thermal-Hydraulic performance of 19 and 61-pin Wire-Wrapped bundles with conjugate heat transfer using RANS. 194:110122-110122. 2023
- A Data-driven approach to predicting neutron penetration through media. 192:109953-109953. 2023
- Proliferation resistance of light water reactor versus pebble bed reactor (vol 188, pg 1, 2023). 190:109882-109882. 2023
- Non-intrusive reduced-order modeling of radiation transport in the atmosphere. 188:109798-109798. 2023
- Proliferation resistance of light water reactor versus pebble bed reactor. 188:109797-109797. 2023
- A sensitivity analysis to predict the neutronics behavior of samples irradiated in the VTR rabbit system. 185:109708-109708. 2023
- Reactor physics analysis of a Source-driven TRIGA configuration in subcritical domain. 186:109787-109787. 2023
- Parametric model-order reduction for radiation transport using multi-resolution proper orthogonal decomposition. 180:109432-109432. 2023
- x-MeRA: Computationally efficient adaptive mesh refinement of Monte Carlo mesh based tallies. 182. 2022
- Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data. 168:108891-108891. 2022
- An uncertainty quantification method relevant to material test reactors. 165:108629-108629. 2022
- Characterization of plutonium for nuclear forensics using machine learning techniques. 170. 2022
- Design and performance analysis of a mobile, land-based micro-reactor. 165:108688-108688. 2022
- Nondestructive and destructive assay for forensics characterization of weapons-grade plutonium produced in LEU irradiated in a thermal neutron spectrum. 183. 2022
- Pressure drop and flow characteristics in partially blocked wire wrapped rod bundles. 165:108671-108671. 2022
- Proliferation resistance assessment of a typical pebble bed reactor fuel. 165. 2022
- The impact of refueling schemes on the proliferation resistance of a pebble bed reactor. 170. 2022
- Improved natural convection heat transfer correlations for reactor cavity cooling systems of high-temperature gas-cooled reactors: From computational fluid dynamics to Pronghorn. 163:108547-108547. 2021
- Two-zone stratified wetwell model development and implementation for RELAP-7. 164:108592-108592. 2021
- A network approach to full core temperature analysis in advanced nuclear heat-pipe systems. 160:108354-108354. 2021
- A novel method for the design and selection of neutron-attenuating media. 160:108368-108368. 2021
- A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis. 160:108393-108393. 2021
- Advanced flow and temperature measurements in a forced convection molten salt test loop. 159:108269-108269. 2021
- Affine reduced-order model for radiation transport problems in cylindrical coordinates. 158:108214-108214. 2021
- A new methodology to estimate stochastic uncertainty of MCNP-predicted isotope concentrations in nuclear fuel burnup simulations. 151. 2021
- Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review. 161. 2021
- Physical anomaly detection and identification using Cerenkov radiation. 142:107424-107424. 2020
- Space-energy separated representations for multigroup neutron diffusion using proper generalized decompositions. 142:107360-107360. 2020
- Three dimensional reactor power profile reconstruction using Cerenkov radiation. 142:107426-107426. 2020
- Experimental measurements of flow mixing in cold leg of a pressurized water reactor. 140:107137-107137. 2020
- Novel design integration for advanced nuclear heat-pipe systems. 141:107324-107324. 2020
- Response function generation for Cerenkov radiation production and transport in a TRIGA coolant channel. 138:107200-107200. 2020
- Spatial power profiling method using visual information in reactors with optically transparent coolants. 137:107071-107071. 2020
- Influence of the spatial Pu variation for evaluating the Pu content in spent nuclear fuel using Support Vector Regression. 135. 2020
- MAPPS: A stochastic computational tool for multi-path analysis of physical protection systems. 137. 2020
- Proliferation resistance evaluation of an HTGR transuranic fuel cycle using PRAETOR code. 141. 2020
- Semi-empirical analysis of the spatial variation of Pu quality ratio in a reactor core for application in pyroprocessing of used nuclear fuel. 138. 2020
- Computational study of full-scale VHTR lower plenum for turbulent mixing assessment. 134:101-113. 2019
- Impact of the volume heat source on the RANS-based CFD analysis of Molten Salt Reactors. 134:376-382. 2019
- Analysis of the transmutation of long lived fission products using a charged particle beam. 133:501-510. 2019
- Design of an experimental facility with a unit cell test section for studies of the lower plenum in prismatic high temperature gas reactors. 133:236-247. 2019
- Novel consistent approach in controllability evaluations of point reactor kinetics models. 131:496-506. 2019
- Multiphysics reactor-core simulations using the improved quasi-static method. 125:186-200. 2019
- Demonstration of LOTUS multiphysics BEPU analysis framework for LB-LOCA simulations. 122:8-22. 2018
- A reduced order accelerator for time-dependent segregated neutronic solvers. 121:177-185. 2018
- Design strategies for LWR and VHTR test environments in a fast spectrum reactor. 120:219-235. 2018
- Numerical analysis of 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event using GOTHIC. 119:46-65. 2018
- Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event. 114:154-164. 2018
- Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor. 113:15-24. 2018
- A neutron transport and thermal hydraulics coupling scheme to study xenon induced power oscillations in a nuclear reactor. 106:64-70. 2017
- Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor. 101:419-428. 2017
- Whether a Theory of Nuclear Safety is deterministic or probabilistic? A metatheory. 110:979-988. 2017
- Neutronics and thermal hydraulics analysis of a small modular reactor. 97:232-245. 2016
- Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform. 96:212-222. 2016
- A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis. 85:27-35. 2015
- Linear regression and sensitivity analysis in nuclear reactor design. 85:798-811. 2015
- Optimization of U-Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms. 85:885-892. 2015
- Parametric evaluation of an SMR design domain. 85:958-978. 2015
- Discontinuous finite element discretizations for the SN neutron transport equation in problems with spatially varying cross sections. 73:506-526. 2014
- Modeling the thermal-hydraulic behavior of the reactor cavity cooling system using RELAP5-3D. 73:75-83. 2014
- Computation fluid dynamics analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-Cooled Reactors. 72:257-267. 2014
- Quantification of US spent fuel inventories in nuclear waste management. 72:277-285. 2014
- Analysis of a sustainable gas cooled fast breeder reactor concept. 69:252-259. 2014
- Experimental study of bypass flow in near wall gaps of a pebble bed reactor using hot wire anemometry technique. 65:60-71. 2014
- Modelling and analysis of the MSFR transient behaviour. 64:485-498. 2014
- Comparative analysis of thorium and uranium fuel for transuranic recycle in a sodium cooled Fast Reactor. 62:26-39. 2013
- Concept of a high temperature integrated multi-modular thermal reactor. 55:312-321. 2013
- Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure. 53:492-506. 2013
- A generalized adjoint framework for sensitivity and global error estimation in time-dependent nuclear reactor simulations. 52:47-58. 2013
- Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with tru-fueled VHTRs. 38:88-97. 2011
- VVER-1000 MOX Core Computational Benchmark analysis using indigenous codes EXCEL, TRIHEX-FA and HEXPIN. 36:1502-1515. 2009
- A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL. 36:505-519. 2009
- A simple Hessian-based 3D mesh adaptation technique with applications to the multigroup diffusion equations. 35:2006-2018. 2008
- KAMINI reactor benchmark analysis. 35:570-575. 2008
- A two-component equilibrium-diffusion limit. 32:233-240. 2005
- Monte Carlo modeling of KAMINI. 31:2185-2194. 2004
- "I have an idea!" An appreciation of Edward W. Larsen's contributions to particle transport. 31:1963-1986. 2004
- A two-component equilibrium-diffusion limit. 31:2049-2057. 2004
- Editorial to: Edward Larsen's 60th birthday. 31:1959-1960. 2004
- Shield structure optimisation studies for the west beam port of the KAMINI reactor. 31:1403-1413. 2004
- View-CXS neutron and photon cross-sections viewer. 31:923-931. 2004
- Optimization of MOX enrichment distributions in typical LWR assemblies using a simplex method-based algorithm. 29:2001-2017. 2002
- A novel concept of passive shutdown heat removal in advanced nuclear reactorsApplications to PRISM and MHTGR. 16:483-486. 1989