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Issues
April 2023
In Progress
ISSN 2332-8983
EISSN 2332-8975
Research Papers
Thermal Hydraulics and CFD
The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.
doi: https://doi.org/10.1115/1.4054546
Topics:
Airfoils
,
Flow (Dynamics)
,
Geometry
,
Stress
,
Heat exchangers
,
Heat transfer
,
Temperature
,
Fluids
,
Structural analysis
Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment
Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.
doi: https://doi.org/10.1115/1.4054685
Reactor Physics
Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
doi: https://doi.org/10.1115/1.4053827
Topics:
Design
,
Vessels
,
Cycles
,
Fuels
,
Temperature
,
Fast neutron reactors
,
Small modular reactors
Plant Systems, O&M, and Life Cycle
Experimental Study on Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021801.
doi: https://doi.org/10.1115/1.4054040
Topics:
Damage
,
Impact testing
,
Projectiles
,
Reinforced concrete
Design Innovation Paper
ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
doi: https://doi.org/10.1115/1.4054726
Topics:
Design
,
Optimization
,
Safety
,
Thermal hydraulics
,
Nuclear design
,
Nuclear reactors
,
Computer simulation
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RSS Feeds
The Heat Capacity of PuO2 at High Temperature: Molecular Dynamics Calculations
ASME J of Nuclear Rad Sci
Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
ASME J of Nuclear Rad Sci (October 2022)
