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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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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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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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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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ACCURACY IMPROVEMENT FOR GAMMA-RAY TECHNIQUES IN TWO-PHASE MEASUREMENT

ANGHAIE, SAMIM

1982

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Reaction of Uranium Hexafluoride Gas with Alumina and Zirconia at Elevated Temperatures

Journal of the American Ceramic Society, 1991-09, Vol.74 (9), p.2250-2257

1991

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Material Characterization and Flaw Detection, Sizing, and Location by the Differential Gamma Scattering Spectroscopy Technique. Part II: Experiment

Nuclear technology, 1990-09, Vol.91 (3), p.376-387

1990

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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

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

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

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

ACCURACY IMPROVEMENT FOR GAMMA-RAY TECHNIQUES IN TWO-PHASE MEASUREMENT

Reaction of Uranium Hexafluoride Gas with Alumina and Zirconia at Elevated Temperatures

Material Characterization and Flaw Detection, Sizing, and Location by the Differential Gamma Scattering Spectroscopy Technique. Part II: Experiment

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