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Journal Articles

Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors

Li Wanai, Gong Helin, Zhang Chunyu

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031503.

Paper No: NERS-21-1114

DOI: https://doi.org/10.1115/1.4055379

Published Online: February 22, 2023

View Article titled, Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors

Topics: Diffusion (Physics), Finite element methods, Neutron flux, Neutrons, Computation, Finite element model

Journal Articles

Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

Md. Tanvir Ahmed, Md. Hossain Sahadath, Md. Ashraful Islam

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031501.

Paper No: NERS-22-1022

DOI: https://doi.org/10.1115/1.4055522

Published Online: February 8, 2023

View Article titled, Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

Topics: Fuels, Cycles, Neutron flux, Neutrons, Manufacturing

Journal Articles

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Eva Vilímová, Tomáš Peltan, Jana Jiřičková

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.

Paper No: NERS-21-1013

DOI: https://doi.org/10.1115/1.4050990

Published Online: June 15, 2022

View Article titled, Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels

Journal Articles

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Nader M. A. Mohamed, Mosa Osman, Ibrahim Abdelrazek

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034503.

Paper No: NERS-21-1109

DOI: https://doi.org/10.1115/1.4054005

Published Online: May 26, 2022

View Article titled, Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Topics: Irradiation (Radiation exposure), Neutron flux, Neutrons, Silicon

Journal Articles

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

Octaviana Erawati Fadli, Azizul Khakim, S. Suharyana, A. Suparmi

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032002.

Paper No: NERS-20-1013

DOI: https://doi.org/10.1115/1.4048904

Published Online: April 1, 2021

View Article titled, Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

Topics: Irradiation (Radiation exposure), Safety, Neutron flux, Fuels, Test facilities

Journal Articles

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Vlastimil Juříček, Michal Košťál, Evžen Losa, Tomáš Czakoj, Zdeněk Matěj, František Cvachovec, Martin Schulc, Jan Šimon, Filip Mravec, Václav Přenosil, Vojtěch Rypar

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022005.

Paper No: NERS-20-1153

DOI: https://doi.org/10.1115/1.4049726

Published Online: February 19, 2021

View Article titled, The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Topics: Filters, Iron, Neutrons, Silicon, Spectra (Spectroscopy), Neutron flux, Steel

Journal Articles

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Zbyněk Hlaváč, Jaroslava Zatloukalová, Michal Košťál, Evžen Losa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022001.

Paper No: NERS-20-1116

DOI: https://doi.org/10.1115/1.4048768

Published Online: October 30, 2020

View Article titled, Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Topics: Concretes, Irradiation (Radiation exposure), Neutrons, Accidents, Neutron flux, Gamma rays, Radiation (Physics)

Journal Articles

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.

Paper No: NERS-19-1079

DOI: https://doi.org/10.1115/1.4046354

Published Online: June 5, 2020

View Article titled, Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Topics: Coolants, Flow (Dynamics), Irradiation (Radiation exposure), Neutron flux, Neutrons, Reactor vessels, Supercritical water reactors, Design, Fuels, Temperature

Journal Articles

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021108.

Paper No: NERS-19-1059

DOI: https://doi.org/10.1115/1.4044910

Published Online: February 5, 2020

View Article titled, Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Topics: Cross section (Physics), Fuels, Simulation, Temperature, Graphite, Neutron flux, Nuclear fission, Neutrons, High temperature, Flow (Dynamics)

Journal Articles

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402.

Paper No: NERS-18-1123

DOI: https://doi.org/10.1115/1.4043100

Published Online: July 19, 2019

View Article titled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

Topics: Atoms, Displacement, Dosimetry, Fluence (Radiation measurement), Fuels, Geometry, Iron, Manufacturing, Modeling, Neutron flux

Journal Articles

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021008.

Paper No: NERS-17-1079

DOI: https://doi.org/10.1115/1.4038653

Published Online: March 5, 2018

View Article titled, The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Topics: Deformation, Diffusion (Physics), Eigenvalues, Neutron flux, Neutrons, Polynomials, Currents, Computational methods, Physics, Nuclear engineering

Journal Articles

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Luigi Lepore, Romolo Remetti

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041018.

Paper No: NERS-17-1017

DOI: https://doi.org/10.1115/1.4037262

Published Online: July 31, 2017

View Article titled, Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Topics: Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Neutrons, Sensors, Signals, Simulation, Instrumentation

Journal Articles

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005.

Paper No: NERS-15-1226

DOI: https://doi.org/10.1115/1.4033813

Published Online: December 20, 2016

View Article titled, Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Topics: High temperature, Neutron flux, Rods, Fuels, Design, Temperature, Computational methods

Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.

Paper No: NERS-16-1007

DOI: https://doi.org/10.1115/1.4034478

Published Online: December 20, 2016

View Article titled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles

Journal Articles

On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

Luigi Lepore, Romolo Remetti, Mauro Cappelli

ASME J of Nuclear Rad Sci. October 2016, 2(4): 041002.

Paper No: NERS-15-1205

DOI: https://doi.org/10.1115/1.4033697

Published Online: October 12, 2016

View Article titled, On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

Topics: Instrumentation, Neutron flux, Neutrons, Sensors

Journal Articles

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

Alberto Sartori, Antonio Cammi, Lelio Luzzi, Gianluigi Rozza

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021019.

Paper No: NERS-14-1062

DOI: https://doi.org/10.1115/1.4031945

Published Online: February 29, 2016

View Article titled, A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

Topics: Eigenvalues, Errors, Modeling, Neutron flux, Nuclear reactors, Rods, Shapes, Approximation, Neutrons, Diffusion (Physics)

Journal Articles

A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor

S. Lorenzi, A. Cammi, L. Luzzi, R. Ponciroli

ASME J of Nuclear Rad Sci. July 2015, 1(3): 031007.

Paper No: NERS-14-1050

DOI: https://doi.org/10.1115/1.4029791

Published Online: May 20, 2015

View Article titled, A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor

Topics: Diffusion (Physics), Eigenfunctions, Fast neutron reactors, Fuels, Modeling, Simulation, Temperature, Transients (Dynamics), Neutron flux, Neutrons

Journal Articles

Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor

Michal Košťál, Vlastimil Juříček, Ján Milčák, Vojtěch Rypar, Antonín Kolros

ASME J of Nuclear Rad Sci. April 2015, 1(2): 024509.

Paper No: NERS-14-1019

DOI: https://doi.org/10.1115/1.4029284

Published Online: March 24, 2015

View Article titled, Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor

Topics: Neutrons, Flux (Metallurgy), Neutron flux

Journal citation

NARROW

Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors

Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Statistical Burnup Distribution of Moving Pebbles in the High-Temperature Reactor HTR-PM

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

The Differences Between the Two Forms of Semi-Analytical Nodal Methods on Solving the Third-Order Simplified Spherical Harmonics Method Equations

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

On Capabilities and Limitations of Current Fast Neutron Flux Monitoring Instrumentation for the Demo LFR ALFRED

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor

Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor

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