Volume 7 Issue 1 | ASME J. of Nuclear Rad Sci.

Topics: China , Nuclear engineering , Nuclear power , Radiation (Physics) , Carbon , Climate change , Construction , Japan Society of Mechanical Engineers , Nuclear industry , Nuclear power stations

Review Article

The Intersection of Advancing Technology and Human Performance

Jonathan K. Corrado

ASME J of Nuclear Rad Sci. January 2021, 7(1): 010801. doi: https://doi.org/10.1115/1.4047717

Abstract

View articletitled, The Intersection of Advancing Technology and Human Performance

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Topics: Errors , Machinery , Human factors , Design

Research Papers

Next Generation/Advanced Reactors

Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

Ganesh V., Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011301. doi: https://doi.org/10.1115/1.4048235

Abstract

View articletitled, Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

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Topics: Temperature , Vessels , Water

Thermal Hydraulics and CFD

Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries

Edward Shitsi, Seth Kofi Debrah, Vincent Yao Agbodemegbe, Emmanuel Ampomah-Amoako

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011401. doi: https://doi.org/10.1115/1.4046255

Abstract

View articletitled, Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries

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Topics: Computational fluid dynamics , Flow (Dynamics) , Flow instability , Gravity (Force) , Oscillations , Pressure , Temperature , Heating , Turbulence , Coolants

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402. doi: https://doi.org/10.1115/1.4047161

Abstract

View articletitled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

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Topics: Accidents , Boiling water reactors , Eigenvalues , Fluids , Porosity , Pressure , Pressurized water reactors , Light water reactors , Water , Stability

Experimental Investigation of Flow Instability Between Two Vertical Parallel Channels Using Supercritical CO₂

Anantvir Singh Saini, Vijay Chatoorgoon, Dhanashree S. Ghadge

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011403. doi: https://doi.org/10.1115/1.4047716

Abstract

View articletitled, Experimental Investigation of Flow Instability Between Two Vertical Parallel Channels Using Supercritical CO2

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Topics: Electricity (Physics) , Flow (Dynamics) , Flow instability , Heating , Pressure , Temperature , Fluids , Oscillations , Valves , Carbon dioxide

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404. doi: https://doi.org/10.1115/1.4047495

Abstract

View articletitled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

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Topics: Boundary-value problems , Computational fluid dynamics , Coolants , Flow (Dynamics) , Geometry , Temperature , Cooling , Temperature distribution , Metals

Reactor Physics

Total Cross Section Phenomenological Formulas for X-Ray and Gamma Radiation Interaction With Matter for Different Energies and Absorber Types

Krzysztof Wojciech Fornalski

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011501. doi: https://doi.org/10.1115/1.4045806

Abstract

View articletitled, Total Cross Section Phenomenological Formulas for X-Ray and Gamma Radiation Interaction With Matter for Different Energies and Absorber Types

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Topics: Approximation , Gamma rays , Photons , Polynomials , Radiation (Physics) , X-rays , Absorption spectra , Photoelectric effect

A Simplified Two-Group Multipoint Kinetics Model

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502. doi: https://doi.org/10.1115/1.4046254

Abstract

View articletitled, A Simplified Two-Group Multipoint Kinetics Model

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Topics: Eigenvalues , Heat flux , Neutrons , Steady state , Transients (Dynamics) , Thermal hydraulics , Diffusion (Physics) , Simulation , Circuits , Fluid dynamics

Nuclear Fuels/Cycles and Materials

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

Lian-Cheng Wang, Matthew H. Kaye

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601. doi: https://doi.org/10.1115/1.4046784

Abstract

View articletitled, The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

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Topics: Nuclear fuels , Phase diagrams , Temperature , Uranium , Modeling , Military systems , Nuclear fission , Spent nuclear fuels

Ni⁺ and He⁺ Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

Maisaa N. Tawfeeq, Robert J. Klassen

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011602. doi: https://doi.org/10.1115/1.4046716

Abstract

View articletitled, Ni+ and He+ Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

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Topics: Alloys , Damage , Electron microscopy , Hardening , Heat , Helium , Ion implantation , Irradiation (Radiation exposure) , Superalloys , Testing

Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603. doi: https://doi.org/10.1115/1.4047919

Abstract

View articletitled, Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

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Topics: Alloys , Creep , Errors , Cathode ray oscilloscopes , Electron beams , High temperature , Corrosion , Melting

Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

Andrew Oussoren, Paul Chan, Diane Wowk, Andrew Prudil

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604. doi: https://doi.org/10.1115/1.4048120

Abstract

View articletitled, Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

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Topics: Failure , Fracture (Materials) , Fuels , Nuclear fission , Diffusion (Physics)

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Yong Lu, Zheng Jiang, Linyang Li, Cuiping Wang, Yihui Guo, Jiajia Han, Xingjun Liu

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605. doi: https://doi.org/10.1115/1.4047718

Abstract

View articletitled, Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

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Topics: Diffusion (Physics) , Irradiation (Radiation exposure) , Phase diagrams , Zirconium

Nuclear Safety/Security and Beyond Design Basis Events

Study on Description of Plant Status at Fukushima Accident by Emergency Action Level

Kazufumi Nagashima, Nakahiro Yasuda

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011701. doi: https://doi.org/10.1115/1.4046841

Abstract

View articletitled, Study on Description of Plant Status at Fukushima Accident by Emergency Action Level

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Topics: Accidents , Emergencies , Evacuations , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Protective actions , Decision making , Uncertainty

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702. doi: https://doi.org/10.1115/1.4046257

Abstract

View articletitled, Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

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Topics: Pipes , Temperature , Vessels , Heavy water reactors

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

R. David

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703. doi: https://doi.org/10.1115/1.4048008

Abstract

View articletitled, Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

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Topics: Accidents , Finite element model , Heat , Melting , Porosity , Temperature , Transients (Dynamics) , Uranium , Materials properties

Plant Systems, O&M, and Life Cycle

Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

Ashok Kumar, Anindya Chatterjee

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801. doi: https://doi.org/10.1115/1.4047494

Abstract

View articletitled, Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

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Topics: Buckling , Shells , Stress , Geometry

Radiation Science

Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities

Angelina-Nataliya V. Vukolova, Andrei A. Rusinkevich

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012001. doi: https://doi.org/10.1115/1.4047044

Abstract

View articletitled, Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities

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Topics: Nuclear power stations , Radioisotopes , Boiling water reactors , Pressurized water reactors

Estimation of Radiological Consequences at a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code

Kwame Gyamfi, Sylvester Attakorah Birikorang, Emmanuel Ampomah-Amoako, John Justice Fletcher

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012002. doi: https://doi.org/10.1115/1.4048026

Abstract

View articletitled, Estimation of Radiological Consequences at a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code

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Topics: Accidents , Meteorology , Nuclear power stations , Radioisotopes , Stability , Coolants , Radiation (Physics) , Plumes (Fluid dynamics) , Water , Evacuations

Fusion Engineering

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301. doi: https://doi.org/10.1115/1.4048007

Abstract

View articletitled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

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Topics: Accidents , Computational fluid dynamics , Design , Flanges , Insulation , Pressure , Stress , Temperature , Temperature gradient , Thermal analysis