Volume 4 Issue 2 | ASME J. of Nuclear Rad Sci.

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Guest Editorial

Special Section: Selected and Revised Papers From ICONE-24

Asif Arastu, Yassin Hasan, Leon Cizelj, Jovica R. Riznic, Guoqiang Wang

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020201. doi: https://doi.org/10.1115/1.4039038

Extract

View articletitled, Special Section: Selected and Revised Papers From ICONE-24

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Topics: Licensing , Nuclear engineering , Plant construction , Safety , Security , Thermal hydraulics

Special Section Papers

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Yuta Abe, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020901. doi: https://doi.org/10.1115/1.4038911

Abstract

View articletitled, Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

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Topics: Heating , Plasmas (Ionized gases) , Boiling water reactors , Accidents

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902. doi: https://doi.org/10.1115/1.4038059

Abstract

View articletitled, Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

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Topics: Aerosols , Containment , Nuclear fission , Temperature , Sensitivity analysis , Water , Condensers (steam plant) , Thermal hydraulics , Condensation

Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions

Laurent Cantrel, Thierry Albiol, Loïc Bosland, Juliette Colombani, Frédéric Cousin, Anne-Cécile Grégoire, Olivia Leroy, Sandrine Morin, Christian Mun, Marie-Noëlle Ohnet, Sidi Souvi, Céline Monsanglant-Louvet, Florent Louis, Bruno Azambre, Christophe Volkringer

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020903. doi: https://doi.org/10.1115/1.4038223

Abstract

View articletitled, Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions

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Topics: Accidents , Aerosols , Containment , Filters , Irradiation (Radiation exposure) , Modeling , Ruthenium , Simulation , Nuclear fission , Nuclear reactor cooling

Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models

Miltiadis Alamaniotis, Mauro Cappelli

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020904. doi: https://doi.org/10.1115/1.4037203

Abstract

View articletitled, Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models

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Topics: Boiling water reactors , Signals

Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

Gueorgui I. Petkov

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020905. doi: https://doi.org/10.1115/1.4039000

Abstract

View articletitled, Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

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Topics: Accidents , Design , Errors , Safety , Scram , Transients (Dynamics) , Water , Pressure , Delays , Valves

Comprehensive Seismic Evaluation of HTTR Against the 2011 Off the Pacific Coast of Tohoku Earthquake

Masato Ono, Kazuhiko Iigaki, Hiroaki Sawahata, Yosuke Shimazaki, Atsushi Shimizu, Hiroyuki Inoi, Toshinari Kondo, Keidai Kojima, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020906. doi: https://doi.org/10.1115/1.4039288

Abstract

View articletitled, Comprehensive Seismic Evaluation of HTTR Against the 2011 Off the Pacific Coast of Tohoku Earthquake

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Topics: Earthquakes , Inspection , Instrumentation , Pacific Ocean , Shorelines , Optical quality control

Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant

Tamás János Katona, András Vilimi

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020907. doi: https://doi.org/10.1115/1.4037715

Abstract

View articletitled, Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant

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Topics: Design , Hazards , Probability , Accident management , Nuclear power stations , Earthquakes

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Rafael Bocanegra, Valentino Di Marcello, Victor H. Sánchez-Espinoza, Gonzalo Jiménez

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020908. doi: https://doi.org/10.1115/1.4038062

Abstract

View articletitled, Fukushima Unit 2 Accident Simulation With MELCOR 2.1

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Topics: Accidents , Containment , Fukushima nuclear disaster, Japan, 2011 , Pressure , Safety , Simulation , Underground injection , Leakage , Pumps , Flow (Dynamics)

Anticipated Operational Occurrences That Could Develop into Serious Accidents

Samuel Miranda

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020909. doi: https://doi.org/10.1115/1.4038160

Abstract

View articletitled, Anticipated Operational Occurrences That Could Develop into Serious Accidents

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Topics: Accidents , Design , Emergency core cooling systems , Flow (Dynamics) , Platform supply vessels , Pressure , Safety , Water , Licensing

Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

Massimo Di Pietro, Sergio Pistelli, Eugenio Garneri, Rosa Lo Frano, Riccardo Ciolini

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020910. doi: https://doi.org/10.1115/1.4038556

Abstract

View articletitled, Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

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Topics: Circuits , Ejectors , Flow (Dynamics) , Nuclear decommissioning , Nuclear power stations , Scrap metals , Suction , Water , Heat shielding

Power Cycle Assessment of Nuclear Systems, Providing Energy Storage for Low Carbon Grids

Nima Fathi, Patrick McDaniel, Charles Forsberg, Cassiano de Oliveira

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020911. doi: https://doi.org/10.1115/1.4037806

Abstract

View articletitled, Power Cycle Assessment of Nuclear Systems, Providing Energy Storage for Low Carbon Grids

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Topics: Co-firing , Cycles , Flow (Dynamics) , Steam , Temperature , Hydrogen , Combined cycles , Carbon

Effect of Soil-Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building

Samer El-Bahey, Yasser Alzeni, Konstantinos Oikonomou

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020912. doi: https://doi.org/10.1115/1.4039076

Abstract

View articletitled, Effect of Soil-Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building

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Topics: Soil , Design , Safety , Earthquakes

Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants

Gueorgui I. Petkov, Monica Vela-Garcia

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020913. doi: https://doi.org/10.1115/1.4038928

Abstract

View articletitled, Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants

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Topics: Accidents , Boiling water reactors , Nuclear power stations , Safety

Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents

L. Sihver, N. Yasuda

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020914. doi: https://doi.org/10.1115/1.4037116

Abstract

View articletitled, Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents

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Topics: Accidents , Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986 , Fukushima nuclear disaster, Japan, 2011 , Safety , Design , Nuclear power stations

Research Papers

Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code

S. P. Saraswat, P. Munsh, A. Khanna, C. Allison

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021001. doi: https://doi.org/10.1115/1.4038823

Abstract

View articletitled, Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified <span class="small-caps">relap/scdapsim/mod</span>4.0 Code

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Topics: Accidents , Coolants , Heat , Helium , Pressure , Vessels , Water , Safety , Temperature , Vacuum

Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Stephen A. Hambric, Samir Ziada, Richard J. Morante

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021002. doi: https://doi.org/10.1115/1.4037898

Abstract

View articletitled, Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

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Topics: Steam , Stress , Boiling water reactors , Dryers

Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

F. Salaun, D. R. Novog

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003. doi: https://doi.org/10.1115/1.4038557

Abstract

View articletitled, Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

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Topics: Blades , Cycles , Design , Fuels , Optimization , Physics , Supercritical water reactors , Temperature , Thermal hydraulics , Coolants

A Comparative Study of Ten Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations

Yining Zhang, Haochun Zhang, Kexin Wang

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021004. doi: https://doi.org/10.1115/1.4038772

Abstract

View articletitled, A Comparative Study of Ten Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations

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Topics: Density , Gears , Neutrons , Polynomials , Runge-Kutta methods , Stiffness , Errors , Numerical analysis

Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

Mukesh Kumar, A. K. Nayak, Sumit V. Prasad, P. K. Verma, R. K. Singh, Vikas Jain, D. K. Chandraker

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021005. doi: https://doi.org/10.1115/1.4038899

Abstract

View articletitled, Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

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Topics: Accidents , Acoustics , Coolants , Design , Flow (Dynamics) , Fuels , Heat , Heavy water reactors , Pipes , Pressure

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

Xie Yang, Ding She, Lei Shi

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021006. doi: https://doi.org/10.1115/1.4038774

Abstract

View articletitled, Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

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Topics: Accidents , Design , Fuels , Nuclear reactors , Neutrons , Temperature , Uranium , Helium , Graphite , Thermal energy

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Jian Li, Ding She, Lei Shi

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021007. doi: https://doi.org/10.1115/1.4038771

Abstract

View articletitled, Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

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Topics: Algorithms , Chain , Errors , Nuclides , Polynomial approximation , Physics

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

Abstract

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

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

Probabilistic-Based Robotic Radiation Mapping Using Sparse Data

Robin McDougall, Scott B. Nokleby, Ed Waller

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021009. doi: https://doi.org/10.1115/1.4038185

Abstract

View articletitled, Probabilistic-Based Robotic Radiation Mapping Using Sparse Data

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Topics: Radiation (Physics) , Sensors , Robotics

Dose Rates From the Accidental Withdrawal of a Fuel Element From an Open Pool-Type Reactor

Amr Abdelhady

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021010. doi: https://doi.org/10.1115/1.4038058

Abstract

View articletitled, Dose Rates From the Accidental Withdrawal of a Fuel Element From an Open Pool-Type Reactor

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Topics: Control rooms , Fuels , Radiation (Physics) , Water

Technical Brief

Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

Xiong Wenbin, Xie Qin, Li Huwei, Yang Sengai, Mao Huan, Cao Jian

ASME J of Nuclear Rad Sci. April 2018, 4(2): 024501. doi: https://doi.org/10.1115/1.4038999

Abstract

View articletitled, Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

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Topics: China , Fast neutron reactors , Safety , Design , Rods

Low-Energy Ion Irradiated Silicon Nanowires: Anomalous Plastic Deformation

Chu Rainer Kwang-Hua

ASME J of Nuclear Rad Sci. April 2018, 4(2): 024502. doi: https://doi.org/10.1115/1.4038336

Abstract

View articletitled, Low-Energy Ion Irradiated Silicon Nanowires: Anomalous Plastic Deformation

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Topics: Deformation , Nanowires , Silicon , Temperature , Viscosity , Flow (Dynamics) , Ions

Guest Editorial

Special Section: Selected and Revised Papers From ICONE-24

Special Section Papers

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions

Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models

Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events

Comprehensive Seismic Evaluation of HTTR Against the 2011 Off the Pacific Coast of Tohoku Earthquake

Design of Severe Accident Management Systems for Beyond Design Basis External Hazards at Paks Nuclear Power Plant

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Anticipated Operational Occurrences That Could Develop into Serious Accidents

Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

Power Cycle Assessment of Nuclear Systems, Providing Energy Storage for Low Carbon Grids

Effect of Soil-Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building

Severe Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants

Causes and Radiological Consequences of the Chernobyl and Fukushima Nuclear Accidents

Research Papers

Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code

Overview of Boiling Water Reactor Steam Dryer Alternating Stress Assessment Procedures

Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

A Comparative Study of Ten Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations

Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

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

Probabilistic-Based Robotic Radiation Mapping Using Sparse Data

Dose Rates From the Accidental Withdrawal of a Fuel Element From an Open Pool-Type Reactor

Technical Brief

Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

Low-Energy Ion Irradiated Silicon Nanowires: Anomalous Plastic Deformation

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