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The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

Nuclear technology, 2010-04, Vol.170 (1), p.68-79

2010

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Foreword: Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants

Nuclear technology, 2010-04, Vol.170 (1), p.1-1

Anghaie, Samim

2010

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SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Nuclear technology, 2010, Vol.170 (1)

ANGHAIE, Samim

2010

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Introduction to the ICAPP '06 Special Issue

Nuclear technology, 2008-10, Vol.164 (1), p.1-2

Anghaie, Samim

2008

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An improved model for two-phase hydrogen flow dynamics

International journal of heat and mass transfer, 2008-06, Vol.51 (11), p.2784-2800

2008

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DEVELOPMENT OF AN AUTOMATED TESTING SYSTEM FOR VERIFICATION AND VALIDATION OF NUCLEAR DATA AND SIMULATION CODE: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Nuclear technology, 2010, Vol.170 (1), p.80-89

2010

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THE ENHANCEMENTS AND TESTING FOR THE MCNPX 2.6.0 DEPLETION CAPABILITY: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Nuclear technology, 2010, Vol.170 (1), p.68-79

2010

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Interaction of Yttria with Uranium Fluoride Gases (UFn, n= 4, 6) at High Temperatures

Journal of the American Ceramic Society, 1994-06, Vol.77 (6), p.1624-1632

1994

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Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code

Nuclear technology, 2010-04, Vol.170 (1), p.80-89

2010

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Improved Reaction Rate Tracking and Fission Product Yield Determinations for the Monte Carlo-Linked Depletion Capability in MCNPX

Nuclear technology, 2008-10, Vol.164 (1), p.3-12

2008

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Processing and fabrication of mixed uranium/refractory metal carbide fuels with liquid-phase sintering

Journal of nuclear materials, 2002-11, Vol.306 (1), p.54-60

2002

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Modification of COMMIX-1B for simulation of thermal- and flowfields in ultrahigh temperature vapor core reactor

Journal of thermophysics and heat transfer, 1991-04, Vol.5 (2), p.242-246

1991

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An effective conduction length model in the enthalpy formulation for the stefan problem

International communications in heat and mass transfer, 2001-08, Vol.28 (6), p.733-741

2001

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Ultrahigh temperature vapor-core reactor - Magnetohydrodynamic system for space nuclear electric power

Journal of propulsion and power, 1993-01, Vol.9 (1), p.98-104

1993

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Numerical Prediction of Multicellular Melt Flow During Natural Convection-Dominated Melting

Journal of thermophysics and heat transfer, 2003-01, Vol.17 (1), p.62-68

2003

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Optimum utilization of nuclear fuel with gas and vapor core reactors

Progress in nuclear energy (New series), 2005-01, Vol.47 (1), p.74-90

2005

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Gas Core Reactor with Magnetohydrodynamic Power System and Cascading Power Cycle

Nuclear technology, 2004-03, Vol.145 (3), p.311-318

2004

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A Computational Fluid Dynamics and Heat Transfer Model for Gaseous Core and Very High Temperature Gas-Cooled Reactors

Nuclear science and engineering, 1998-11, Vol.130 (3), p.361-373

1998

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NUMERICAL MODELLING OF CONDUCTION-DRIVEN BULK EVAPORATION AND CONDENSATION PROCESSES WITH CONSTANT VOLUME

International journal for numerical methods in engineering, 1996-01, Vol.39 (2), p.219-233

1996

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An experimental study of electrical impedance tomography for the two-phase flow visualization

International communications in heat and mass transfer, 2002-02, Vol.29 (2), p.193-202

2002

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Iterative reconstruction and statistical optimization for the nondestructive assay of distributed gamma source in a large nuclear waste container

IEEE transactions on nuclear science, 1998-04, Vol.45 (2), p.146-153

1998

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Thermal-Hydraulic Analysis of Bulk Evaporation and Condensation in a Multiphase Nuclear Fuel Cell

Nuclear technology, 1997-10, Vol.120 (1), p.57-70

1997

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ChemInform Abstract: Status of Advanced Carbide Fuels: Past, Present, and Future

ChemInform, 2002-06, Vol.33 (25), p.no-no

2002

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A High-Definition Gamma Scanning Method for the Near-Field Nondestructive Assay of Large Nuclear Waste Barrels

Nuclear technology, 1998-12, Vol.124 (3), p.265-275

1998

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Development of a Numerical Experiment Technique to Solve Inverse Gamma-Ray Transport Problems with Application to Nondestructive Assay of Nuclear Waste Barrels

Nuclear science and engineering, 1998-03, Vol.128 (3), p.297-311

1998

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The Enhancements and Testing for the MCNPX 2.6.0 Depletion Capability

Foreword: Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants

SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Introduction to the ICAPP '06 Special Issue

An improved model for two-phase hydrogen flow dynamics

DEVELOPMENT OF AN AUTOMATED TESTING SYSTEM FOR VERIFICATION AND VALIDATION OF NUCLEAR DATA AND SIMULATION CODE: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

THE ENHANCEMENTS AND TESTING FOR THE MCNPX 2.6.0 DEPLETION CAPABILITY: SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Interaction of Yttria with Uranium Fluoride Gases (UFn, n= 4, 6) at High Temperatures

Development of an Automated Testing System for Verification and Validation of Nuclear Data and Simulation Code

Improved Reaction Rate Tracking and Fission Product Yield Determinations for the Monte Carlo-Linked Depletion Capability in MCNPX

Processing and fabrication of mixed uranium/refractory metal carbide fuels with liquid-phase sintering

Modification of COMMIX-1B for simulation of thermal- and flowfields in ultrahigh temperature vapor core reactor

An effective conduction length model in the enthalpy formulation for the stefan problem

Ultrahigh temperature vapor-core reactor - Magnetohydrodynamic system for space nuclear electric power

Numerical Prediction of Multicellular Melt Flow During Natural Convection-Dominated Melting

Optimum utilization of nuclear fuel with gas and vapor core reactors

Gas Core Reactor with Magnetohydrodynamic Power System and Cascading Power Cycle

A Computational Fluid Dynamics and Heat Transfer Model for Gaseous Core and Very High Temperature Gas-Cooled Reactors

NUMERICAL MODELLING OF CONDUCTION-DRIVEN BULK EVAPORATION AND CONDENSATION PROCESSES WITH CONSTANT VOLUME

An experimental study of electrical impedance tomography for the two-phase flow visualization

Iterative reconstruction and statistical optimization for the nondestructive assay of distributed gamma source in a large nuclear waste container

Thermal-Hydraulic Analysis of Bulk Evaporation and Condensation in a Multiphase Nuclear Fuel Cell

ChemInform Abstract: Status of Advanced Carbide Fuels: Past, Present, and Future

A High-Definition Gamma Scanning Method for the Near-Field Nondestructive Assay of Large Nuclear Waste Barrels

Development of a Numerical Experiment Technique to Solve Inverse Gamma-Ray Transport Problems with Application to Nondestructive Assay of Nuclear Waste Barrels

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