Volume 8 Issue 2 | ASME J. of Nuclear Rad Sci.

In Memoriam

In Memoriam: Professor Pavel Leonidovich Kirillov (Aug. 20, 1927–Oct. 10, 2021)

Igor Pioro, Romney B. Duffey, Viktor Murogov, Georgy Tikhomirov, Anton Smirnov, Eugen N. Pismennyi, Victor G. Razumovskiy, Natalia Kozioura

ASME J of Nuclear Rad Sci. April 2022, 8(2): 020101. doi: https://doi.org/10.1115/1.4053476

Extract

View articletitled, In Memoriam: Professor Pavel Leonidovich Kirillov (Aug. 20, 1927–Oct. 10, 2021)

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Topics: Engineering teachers

Research Papers

Next Generation/Advanced Reactors

Molecular Dynamics of Supercritical Water for Nuclear Data Development

Katy Hartling, Gang Li, Ghaouti Bentoumi, Zahra Yamani

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021301. doi: https://doi.org/10.1115/1.4051790

Abstract

View articletitled, Molecular Dynamics of Supercritical Water for Nuclear Data Development

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Topics: Molecular dynamics simulation , Simulation , Statistical process control , Water , Electromagnetic scattering , Radiation scattering , Scattering (Physics)

A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

Venkata Rajesh Saranam, Peter Carter, Kyle A. Rozman, Ömer N. Doğan, Brian K. Paul

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021302. doi: https://doi.org/10.1115/1.4050421

Abstract

View articletitled, A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications

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Topics: Bonding , Creep , Design , Diffusion bonding (Metals) , Fatigue , Heat exchangers , Rupture , Temperature , Stress , Pressure

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303. doi: https://doi.org/10.1115/1.4051612

Abstract

View articletitled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

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Topics: Design , Displacement , Fuels , Geometry , Heat , Heat pipes , Molten salt reactors , Nuclear fission , Pipes , Temperature

Thermal Hydraulics and CFD

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401. doi: https://doi.org/10.1115/1.4050209

Abstract

View articletitled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

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Topics: Boundary-value problems , Simulation , Wetting , Vapors , Bubbles , Simulation results

Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

Dong Yang, Jiaxiang Chen, Yongchang Feng, Lin Chen

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021402. doi: https://doi.org/10.1115/1.4051248

Abstract

View articletitled, Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

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Topics: Heat transfer , Turbulence , Water , Temperature , Computer simulation , Heat flux , Heat , Density , Flow (Dynamics) , Viscosity

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403. doi: https://doi.org/10.1115/1.4051875

Abstract

View articletitled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

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Topics: Film boiling , Heat flux , Heat transfer , Pool boiling , Quenching (Metalworking) , Temperature , Transients (Dynamics) , Water , Heat conduction , Heat transfer coefficients

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404. doi: https://doi.org/10.1115/1.4050770

Abstract

View articletitled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

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Topics: Accidents , Coolants , Steady state , Transients (Dynamics) , Errors , Flow (Dynamics) , Thermal hydraulics , Leakage , Simulation

Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design

Lan Qin Yuan, Jun Yang, Bruce Addicott, Matthew Dickerson, Vinson Gauthier

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021405. doi: https://doi.org/10.1115/1.4052521

Abstract

View articletitled, Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design

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Topics: Critical heat flux , Fuels , Pressure , Flow (Dynamics)

Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation

Sundar Namala, Rizwan Uddin

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021406. doi: https://doi.org/10.1115/1.4051928

Abstract

View articletitled, Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation

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Topics: Finite element methods

Reactor Physics

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

D. Ray, S. P. Saraswat, M. Kumar, O. P. Singh, P. Munshi

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501. doi: https://doi.org/10.1115/1.4049727

Abstract

View articletitled, Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

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Topics: Density , Neutrons , Steady state , Transients (Dynamics) , Waves

Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O₂ Fuel Pellets

C. V. Anghel, B. P. Bromley, A. A. Prudil, M. J. Welland

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021502. doi: https://doi.org/10.1115/1.4050767

Abstract

View articletitled, Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O<sub>2</sub> Fuel Pellets

Supplementary data

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Topics: Fuels , Machine learning , Physics , Power density , Neutrons , Heavy water reactors

Nuclear Fuels/Cycles and Materials

Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles

Lei Lou, Xiaoming Chai, Dong Yao, Xingjie Peng, Mancang Li, Liang Chen, Yingrui Yu, Lianjie Wang

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021601. doi: https://doi.org/10.1115/1.4051724

Abstract

View articletitled, Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles

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Topics: Fuels , Particulate matter

Nuclear Safety/Security and Beyond Design Basis Events

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701. doi: https://doi.org/10.1115/1.4051443

Abstract

View articletitled, Post-Test Analyses of the CMMR-4 Test

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Topics: Blades , Boiling water reactors , Cutting , Fuels , Heating , Melting , Water , Temperature , Accidents , Permeability

Plant Systems, O&M, and Life Cycle

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801. doi: https://doi.org/10.1115/1.4051618

Abstract

View articletitled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

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Topics: Aerosols , Boilers , Decontamination , Nuclides , Particulate matter , Pressurized water reactors , Turbulence , Computational fluid dynamics , Flow (Dynamics) , Particle size

RAW Management and Decommissioning

Utilizing of Spent Fuel Storage Pool in Gamma Irradiation Experiments

Amr Abdelhady

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021901. doi: https://doi.org/10.1115/1.4051065

Abstract

View articletitled, Utilizing of Spent Fuel Storage Pool in Gamma Irradiation Experiments

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Topics: Irradiation (Radiation exposure) , Spent nuclear fuels

Radiation Science

Actinide in Air (Rn-Progeny Rejected) Alpha Spectroscopy With Tensioned Metastable Fluid Detectors

M. Hemesath, N. Boyle, B. Archambault, C. Troy Lorier, D. DiPrete, R. P. Taleyarkhan

ASME J of Nuclear Rad Sci. April 2022, 8(2): 022001. doi: https://doi.org/10.1115/1.4049729

Abstract

View articletitled, Actinide in Air (Rn-Progeny Rejected) Alpha Spectroscopy With Tensioned Metastable Fluid Detectors

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Topics: Fluids , Sensors , Spectroscopy , Filters

Code and Regulatory Issues

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Andy Jansky, Magnus Langenstein

ASME J of Nuclear Rad Sci. April 2022, 8(2): 022101. doi: https://doi.org/10.1115/1.4051619

Abstract

View articletitled, Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

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Topics: Measurement uncertainty , Nuclear power stations , Uncertainty , Safety , Feedwater , Flow (Dynamics)

Technical Briefs

Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

Boris Haranki, Ufuk Dilek

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024501. doi: https://doi.org/10.1115/1.4051363

Abstract

View articletitled, Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

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Topics: ASTM International , Concretes , Design , Flow (Dynamics) , Nuclear construction , Pumps , Stability

Proactive Human Error Reduction Using the Systems Engineering Process

Jonathan K. Corrado

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024502. doi: https://doi.org/10.1115/1.4051362

Abstract

View articletitled, Proactive Human Error Reduction Using the Systems Engineering Process

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Topics: Design , Errors , Systems engineering

Thermal Soil Radon Mitigation

Francisco J. Arias, Salvador De Las Heras

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024503. doi: https://doi.org/10.1115/1.4050832

Abstract

View articletitled, Thermal Soil Radon Mitigation

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Topics: Diffusion (Physics) , Soil , Temperature , Rocks , Temperature gradient

The Incorporation of Human Performance Improvement into Systems Design

Jonathan K. Corrado

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024504. doi: https://doi.org/10.1115/1.4051792

Abstract

View articletitled, The Incorporation of Human Performance Improvement into Systems Design

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Topics: Design , Errors

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505. doi: https://doi.org/10.1115/1.4052591

Abstract

View articletitled, On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

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Topics: Coolants , Currents , Design , Excitation , Liquid metals , Magnetic fields , Pressure , Sodium , Heat exchangers , Pumps

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506. doi: https://doi.org/10.1115/1.4053334

Abstract

View articletitled, A Short Inroad to Optimized Compactification of Composite Neutronic Shields

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Topics: Composite materials , Design , Neutrons , Optimization , Neutron beams , Diffusion (Physics) , Weight (Mass)

Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code

A. S. Bikeev, Yu. S. Daichenkova, M. A. Kalugin, D. A. Shkarovsky, V. V. Shkityr

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024507. doi: https://doi.org/10.1115/1.4052340

Abstract

View articletitled, Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code

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Topics: Approximation , Cross section (Physics) , Electromagnetic scattering , Errors , Neutrons , Radiation scattering , Scattering (Physics) , Fuels , Anisotropy

Issues

In Memoriam

Research Papers

Next Generation/Advanced Reactors

Thermal Hydraulics and CFD

Reactor Physics

Nuclear Fuels/Cycles and Materials

Nuclear Safety/Security and Beyond Design Basis Events

Plant Systems, O&M, and Life Cycle

RAW Management and Decommissioning

Radiation Science

Code and Regulatory Issues

Technical Briefs

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