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Issues
July 2023
ISSN 2332-8983
EISSN 2332-8975
Research Papers
Next Generation/Advanced Reactors
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
doi: https://doi.org/10.1115/1.4056930
Topics:
Coolants
,
Density
,
Feedback
,
Fuels
,
Sodium fast reactors
,
Temperature
,
Thermal expansion
,
Manufacturing
,
Electrical conductance
,
Heat
Thermal Hydraulics and CFD
Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
doi: https://doi.org/10.1115/1.4056463
Topics:
Ducts
,
Flow (Dynamics)
,
Fuels
,
Manufacturing
,
Sodium fast reactors
,
Temperature
,
Temperature distribution
,
Thermal hydraulics
,
Wire
,
Fuel rods
Machine Learning Metamodel of a Computationally Intense LOCA Code
Landon A. Conner, Clarence L. Worrell, Jun Liao, James P. Spring, Reza A. Karimi, Jeremy S. Marquardt, Joseph D. Wieder
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031402.
doi: https://doi.org/10.1115/1.4056465
Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
doi: https://doi.org/10.1115/1.4056239
Topics:
Fluids
,
Heat transfer
,
Particulate matter
,
Simulation
,
Temperature
,
Flow (Dynamics)
,
Design
,
Fuels
,
Safety
,
Natural convection
Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031404.
doi: https://doi.org/10.1115/1.4055932
Topics:
Bubbles
,
Bubbly flow
,
Fluids
,
Pressure
,
Simulation
,
Plumes (Fluid dynamics)
,
Porosity
,
Surface tension
,
Flow (Dynamics)
,
Two-phase flow
Reactor Physics
Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031501.
doi: https://doi.org/10.1115/1.4055522
Topics:
Fuels
,
Cycles
,
Neutron flux
,
Neutrons
,
Manufacturing
Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031502.
doi: https://doi.org/10.1115/1.4056603
Topics:
Fuel management
,
Fuels
,
Cross section (Physics)
,
Cycles
Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.
doi: https://doi.org/10.1115/1.4055379
Topics:
Diffusion (Physics)
,
Finite element methods
,
Neutron flux
,
Neutrons
,
Computation
,
Finite element model
Nuclear Fuels/Cycles and Materials
Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031601.
doi: https://doi.org/10.1115/1.4055585
Plant Systems, O&M, and Life Cycle
Long-Term Performance of Semimetallic Gaskets
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.
doi: https://doi.org/10.1115/1.4056260
Topics:
Gaskets
,
Graphite
,
Leakage
,
Temperature
,
Relaxation (Physics)
,
High temperature
,
Weight (Mass)
,
Stress
Radiation Science
Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252Cf Source in Center
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.
doi: https://doi.org/10.1115/1.4056508
Topics:
Copper
,
Leakage
,
Neutrons
,
Uncertainty
,
Spectra (Spectroscopy)
,
Neutron sources
Design and Development of Children's Calibration Phantoms for Whole and Mobile Body Counters
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032002.
doi: https://doi.org/10.1115/1.4055523
Topics:
Calibration
,
Phantoms
Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032003.
doi: https://doi.org/10.1115/1.4056464
Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032004.
doi: https://doi.org/10.1115/1.4056835
Topics:
Absorption
,
Atomic number
,
Computer software
,
Neutrons
,
Photons
,
Radiation (Physics)
A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032005.
doi: https://doi.org/10.1115/1.4056972
Topics:
Algorithms
,
Density
,
Photons
,
X-rays
,
Errors
Technical Brief
Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.
doi: https://doi.org/10.1115/1.4055931
Book Review
Handbook of Generation IV Nuclear Reactors Edition 2
ASME J of Nuclear Rad Sci. July 2023, 9(3): 036501.
doi: https://doi.org/10.1115/1.4062402
Topics:
Generation IV reactors
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A mathematical model design for Pu content analyzed by 244Cm in spent fuel of fast reactors
ASME J of Nuclear Rad Sci
K-Edge Measurement Technology Simulation Model Design
ASME J of Nuclear Rad Sci
Silicate glass reinforced by Bi and B as efficient protective materials against gamma rays and neutrons
ASME J of Nuclear Rad Sci