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Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1161

DOI: https://doi.org/10.1115/1.4056834

Published Online: February 4, 2023

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Topics: Accidents, Fast neutron reactors, Fuels, Pins (Engineering), Safety, Transients (Dynamics), Alloys, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Gravity (Force)

Journal Articles

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code BATAN-FUEL

Surian Pinem, Donny Hartanto, Liem Peng Hong, Wahid Luthfi

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1040

DOI: https://doi.org/10.1115/1.4056603

Published Online: January 5, 2023

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Topics: Cross section (Physics), Fuel management, Fuels

Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1137

DOI: https://doi.org/10.1115/1.4056772

Published Online: January 1, 2023

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Topics: Design, Supercritical carbon dioxide, Coolants, Feedback, Diluents, Fuels, Leakage, Neutrons, Cross section (Physics), Nuclear fission

Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block with 252cf Source in Center

Tomas Czakoj, Michal Kostal, Martin Schulc, Vojtech Rypar, Evzen Novak, Evzen Losa

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1038

DOI: https://doi.org/10.1115/1.4056508

Published Online: December 16, 2022

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Topics: Copper, Leakage, Neutrons, Uncertainty, Density, Calibration, Cross section (Physics), Engineering simulation, Manufacturing, Nuclear industry

Journal Articles

Machine Learning Metamodel of a Computationally Intense Accident Simulation Code

Landon A Conner, Clarence Worrell, Jun Liao, James P. Spring, Reza A. Karimi, Jeremy Marquardt, Joseph D. Wieder

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1002

DOI: https://doi.org/10.1115/1.4056465

Published Online: December 13, 2022

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Topics: Accidents, Machine learning, Simulation, Artificial neural networks, Manufacturing, Optimization, Safety, Approximation, Coolants, Decision analysis

Journal Articles

Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application

Akanchha Fnu, Vikesh Singh Bhadouria, Arun Kumar Pandey, Pankaj Wahi, Niraj Sinha, Prabhat Munshi

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1091

DOI: https://doi.org/10.1115/1.4056464

Published Online: December 13, 2022

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Topics: Calibration, Gates (Closures), Radiation (Physics), Sensors, Uranium, Containers, Data acquisition systems, Design, Inspection, Radioisotopes

Journal Articles

Investigation On Applicability of Subchannel Analysis Code Asfre to Thermal Hydraulics Analysis in Fuel Assembly with Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1158

DOI: https://doi.org/10.1115/1.4056463

Published Online: December 13, 2022

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Topics: Ducts, Fuels, Manufacturing, Sodium fast reactors, Thermal hydraulics, Design, Temperature distribution, Computational fluid dynamics, Computer simulation, Flow (Dynamics)

Journal Articles

Long-Term Performance of Semi-Metallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1036

DOI: https://doi.org/10.1115/1.4056260

Published Online: November 15, 2022

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Topics: Gaskets, Graphite, Leakage, Temperature, High temperature, Relaxation (Physics), Weight (Mass), Creep, Metals, Oxidation

Journal Articles

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

Olugbenga O Noah, Johan . F Slabber, Josua P Meyer

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1020

DOI: https://doi.org/10.1115/1.4056239

Published Online: November 14, 2022

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Topics: Computer simulation, Heat transfer, Natural convection, Safety, Water, Particulate matter, Cladding systems (Building), Fuels, Nuclear fuels, Light water reactors

Journal Articles

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Akinori Tamura, Kenichi Katono

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1052

DOI: https://doi.org/10.1115/1.4055932

Published Online: October 11, 2022

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Topics: Fluids, Simulation, Two-phase flow, Bubbles, Flow (Dynamics), Pressure, Bubbly flow, Modeling, Plumes (Fluid dynamics), Computer simulation

Journal Articles

Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach

Alberto D'Ansi Mendoza España

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1023

DOI: https://doi.org/10.1115/1.4055585

Published Online: September 13, 2022

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Topics: Economics , Uranium, Climate change, Cycles, Governments, Nuclear fuels, Nuclear reactors, Public policy, Stability

Journal Articles

Design and Development of Children's Calibration Phantoms for Whole and Mobile Body Counters

Vaibhav Sinha, Ulrich Scherer

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1047

DOI: https://doi.org/10.1115/1.4055523

Published Online: September 5, 2022

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Topics: Calibration, Design, Phantoms, Accidents, Weight (Mass), Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Construction, Contamination, Explosions, Fukushima nuclear disaster, Japan, 2011

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.

Paper No: NERS-22-1022

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

Published Online: September 5, 2022

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Topics: Fuels, Cycles, Fuel rods, Leakage, Manufacturing, Neutron flux, Neutrons, Particulate matter, Physics, Simulation

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.

Paper No: NERS-21-1114

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

Published Online: August 26, 2022

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Topics: Diffusion (Physics), Finite element methods, Neutrons, Errors, Boundary-value problems, Computation, Cross section (Physics), Design, Eigenvalues, Finite element analysis

Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

DOI: https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

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Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Journal Articles

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Emmanuel O. Osigwe, Arnold Gad-Briggs, Dodeye Igbong, Theoklis Nikolaidis, Pericles Pilidis

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021201.

Paper No: NERS-19-1042

DOI: https://doi.org/10.1115/1.4044260

Published Online: February 24, 2020

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Topics: Cycles, Pressure, Stress, Temperature, Flow (Dynamics), Compressors, Power stations, Heat, Modeling, Closed-cycle gas turbines

Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.

Paper No: NERS-19-1024

DOI: https://doi.org/10.1115/1.4045035

Published Online: February 24, 2020

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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality

Journal Articles

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Hai Quan Ho, Yuki Honda, Shimpei Hamamoto, Toshiaki Ishii, Shoji Takada, Nozomu Fujimoto, Etsuo Ishitsuka

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021902.

Paper No: NERS-19-1040

DOI: https://doi.org/10.1115/1.4044529

Published Online: February 24, 2020

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Topics: Irradiation (Radiation exposure), Neutrons, Silicon, Solar cells, High temperature, Particulate matter

Journal Articles

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

David William Hummel, David Raymond Novog

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403.

Paper No: NERS-18-1008

DOI: https://doi.org/10.1115/1.4042597

Published Online: September 3, 2019

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Topics: Blades, Coolants, Flow (Dynamics), Fuels, Neutrons, Supercritical water reactors, Thermal hydraulics, Transients (Dynamics), Water, Delays

Journal Articles

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Milorad B. Dzodzo, Francesco Oriolo, Walter Ambrosini, Marco Ricotti, Davor Grgic, Roberta Ferri, Andrea Achilli, Fosco Bianchi, Paride Meloni

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208.

Paper No: NERS-18-1027

DOI: https://doi.org/10.1115/1.4042496

Published Online: September 3, 2019

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Topics: Containment vessels, Engineering prototypes, Pressure, Reactor vessels, Test facilities, Transients (Dynamics), Water, Design, Heat, Containment

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Journal citation

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Manuscript

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code BATAN-FUEL

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block with 252cf Source in Center

Machine Learning Metamodel of a Computationally Intense Accident Simulation Code

Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application

Investigation On Applicability of Subchannel Analysis Code Asfre to Thermal Hydraulics Analysis in Fuel Assembly with Inner Duct Structure of Sodium Cooled Fast Reactor

Long-Term Performance of Semi-Metallic Gaskets

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

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach

Design and Development of Children's Calibration Phantoms for Whole and Mobile Body Counters

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

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

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Performance Modeling and Analysis of a Single-Shaft Closed-Cycle Gas Turbine Using Different Operational Control Strategy

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

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