Volume 3 Issue 3 | ASME J. of Nuclear Rad Sci.

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Guest Editorial

Special Section: Selected Papers from the 28th Conference of the Nuclear Societies in Israel

Ilan Yaar, Jean Koch

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030301. doi: https://doi.org/10.1115/1.4036459

Extract

View articletitled, Special Section: Selected Papers from the 28th Conference of the Nuclear Societies in Israel

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Topics: Nuclear engineering , Radiation (Physics) , Biomedicine , Engineering teachers

Special Section Papers

Novel Genetic Algorithms for Loading Pattern Optimization Using State-of-the-Art Operators and a Simple Test Case

Ella Israeli, Erez Gilad

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030901. doi: https://doi.org/10.1115/1.4035883

Abstract

View articletitled, Novel Genetic Algorithms for Loading Pattern Optimization Using State-of-the-Art Operators and a Simple Test Case

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Topics: Algorithms , Genetic algorithms , Optimization , Probability , Fuels , Pressurized water reactors , Gases

Nozzle Geometry Effect on Stratified Layer Erosion by Vertical Turbulent Jet

L. Ishay, U. Bieder, G. Ziskind, A. Rashkovan

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030902. doi: https://doi.org/10.1115/1.4035693

Abstract

View articletitled, Nozzle Geometry Effect on Stratified Layer Erosion by Vertical Turbulent Jet

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Topics: Geometry , Nozzles , Turbulence , Flow (Dynamics) , Jets , Erosion , Buoyancy

Integrated Blast Resistance Model of Nuclear Power Plant Auxiliary Facilities

Irad Brandys, David Ornai, Yigal Ronen

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030903. doi: https://doi.org/10.1115/1.4035692

Abstract

View articletitled, Integrated Blast Resistance Model of Nuclear Power Plant Auxiliary Facilities

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Topics: Damage , Explosions , Nuclear power stations , Shock (Mechanics) , Shear (Mechanics) , Control rooms , Pressure , Rotation , Structural dynamics , Degrees of freedom

Impact From Fly Ash as Additive to Concrete on the Radiation Exposure in Dwellings

Govert de With

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030904. doi: https://doi.org/10.1115/1.4036322

Abstract

View articletitled, Impact From Fly Ash as Additive to Concrete on the Radiation Exposure in Dwellings

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Topics: Concretes , Fly ash , Modeling , Radiation (Physics) , Testing

Minimizing Ionizing Radiation Exposure in Invasive Cardiology Safety Training for Medical Doctors

Aric Katz, Avraham Shtub, Ariel Roguin

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030905. doi: https://doi.org/10.1115/1.4036431

Abstract

View articletitled, Minimizing Ionizing Radiation Exposure in Invasive Cardiology Safety Training for Medical Doctors

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Topics: Biomedicine , Ionizing radiation , Radiation (Physics) , Safety , Machinery

A Study of the External Exposure Decay Curves as a Function of Several Clinical Parameters for Patients Treated With Therapeutic ¹³¹I

Dimitry Ginzburg, Sophia Lantsberg, Sergio Faermann

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030906. doi: https://doi.org/10.1115/1.4036433

Abstract

View articletitled, A Study of the External Exposure Decay Curves as a Function of Several Clinical Parameters for Patients Treated With Therapeutic 131I

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Topics: Biomedicine , Half-life , Radiation (Physics) , Weight (Mass) , Cancer , Fittings

Cesium and Strontium Immobilization in Portland Cement Pastes Blended With Pozzolanic Additives

Gabriela Bar-Nes, Yael Peled, Zorik Shamish, Amnon Katz

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030907. doi: https://doi.org/10.1115/1.4035415

Abstract

View articletitled, Cesium and Strontium Immobilization in Portland Cement Pastes Blended With Pozzolanic Additives

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Topics: Cements (Adhesives) , Diffusion (Physics) , Ions , Slag cement , Strontium , Thermal analysis

How Thick Should Cover Layer be for Radioactive Waste Disposal Facility? The Case of the Yamin Plain, Israel

Avraham Dody, Ravid Rosenzweig, Ran Calvo, Eyal Shalev

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030908. doi: https://doi.org/10.1115/1.4035405

Abstract

View articletitled, How Thick Should Cover Layer be for Radioactive Waste Disposal Facility? The Case of the Yamin Plain, Israel

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Topics: Erosion , Radioactive waste disposal , Soil , Water , Radioactive wastes , Luminescence , Flow (Dynamics)

Evaluation of Hydrogel Technologies for the Decontamination of ¹³⁷Cs From Building Material Surfaces

Ilan Yaar, Rony Hakmon, Itzhak Halevy, Ronen Bar-Ziv, Noah Vainblat, Yacov Iflach, Maor Assulin, Tzipora Avraham, Michael D. Kaminski, Terry Stilman, Shannon Serre

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030909. doi: https://doi.org/10.1115/1.4036458

Abstract

View articletitled, Evaluation of Hydrogel Technologies for the Decontamination of 137Cs From Building Material Surfaces

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Topics: Decontamination , Concretes , Radioisotopes , Hydrogels , Ceramics

Fission Track Detection Using Automated Microscopy

Aryeh M. Weiss, Itzhak Halevy, Naida Dziga, Ernesto Chinea-Cano, Uri Admon

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030910. doi: https://doi.org/10.1115/1.4036434

Abstract

View articletitled, Fission Track Detection Using Automated Microscopy

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Topics: Image processing , Image segmentation , Imaging , Microscopy , Nuclear fission , Particulate matter , Resolution (Optics) , Sensors , Workflow , Forensic sciences

Detection of Combined n/γ Fission Signatures Induced by an Epithermal Neutron Source

A. Ocherashvili, T. Bogucarska, A. Beck, G. Heger, M. Mosconi, E. Roesgen, J.-M. Crochemore, V. Mayorov, G. Varasino, B. Pedersen

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030911. doi: https://doi.org/10.1115/1.4036698

Abstract

View articletitled, Detection of Combined n/γ Fission Signatures Induced by an Epithermal Neutron Source

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Topics: Neutron sources , Neutrons , Nuclear fission , Photons , Signals , Sensors , Scintillation counters

Optimization of a Multiline Neutron Source Based on a ²³²Th Filter

Y. Ben-Galim, R. Moreh, I. Orion

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030912. doi: https://doi.org/10.1115/1.4036435

Abstract

View articletitled, Optimization of a Multiline Neutron Source Based on a 232Th Filter

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Topics: Filters , Neutron sources , Neutrons , Optimization

Ni Interlayer to Improve Low-Pressure Diffusion Bonding of 316L SS Press Fit Tube-to-Tubesheet Joints for Coiled Tube Gas Heaters

Rony Reuven, Alan Bolind, Nils Haneklaus, Cristian Cionea, Charalampos Andreades, Grant Buster, Peter Hosemann, Per Peterson

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030913. doi: https://doi.org/10.1115/1.4035725

Abstract

View articletitled, Ni Interlayer to Improve Low-Pressure Diffusion Bonding of 316L SS Press Fit Tube-to-Tubesheet Joints for Coiled Tube Gas Heaters

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Topics: Diffusion bonding (Metals) , Press fits , Pressure , Stainless steel , Manufacturing , Heat exchangers , Nickel , Testing , Surface roughness

Resistance Improvement of Aluminum Surface to Corrosion Through Reactions With Fluoride Ions

Magal Saphier, Oron Zamir, Polina Berzansky, Oshra Saphier, Dan Meyerstein

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030914. doi: https://doi.org/10.1115/1.4036432

Abstract

View articletitled, Resistance Improvement of Aluminum Surface to Corrosion Through Reactions With Fluoride Ions

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Topics: Aluminum , Ions , Corrosion , Potassium

Safety Improvement to Israel Research Reactor 2 by Increasing the Robustness of Equipment to Ground Acceleration

A. Biton, Y. Soffer, R. Freud

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030915. doi: https://doi.org/10.1115/1.4035568

Abstract

View articletitled, Safety Improvement to Israel Research Reactor 2 by Increasing the Robustness of Equipment to Ground Acceleration

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Topics: Robustness , Safety , Heat

An Improved Method for Estimating the Dose to the Lens of the Eye Using Hp(10) and Hp(0.07) Measurements

Peri Eyal, Abraham Adi, Kravchik Tuvia, Weinstein Marcelo, Sattinger Daniel, Pelled Omer

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030916. doi: https://doi.org/10.1115/1.4036137

Abstract

View articletitled, An Improved Method for Estimating the Dose to the Lens of the Eye Using Hp(10) and Hp(0.07) Measurements

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Topics: Lenses (Optics) , Radiation (Physics) , Dosimeters

Effective Dose Reduction in Lateral Lumbar Spine Diagnostic Radiography Using X-Ray Tube Heel Effect

Avi Ben-Shlomo, Gabriel Bartal, Morris Mosseri, Shay Shabat

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030917. doi: https://doi.org/10.1115/1.4036462

Abstract

View articletitled, Effective Dose Reduction in Lateral Lumbar Spine Diagnostic Radiography Using X-Ray Tube Heel Effect

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Topics: Diagnostic radiography , Lumbar spine , X-rays , Anodes , Radiation (Physics) , Simulation

The Standard for Radiation Protection of the IAEC as a Model for a Revision of the Legal Framework for Radiation Safety in Israel

Jean Koch

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030918. doi: https://doi.org/10.1115/1.4036463

Abstract

View articletitled, The Standard for Radiation Protection of the IAEC as a Model for a Revision of the Legal Framework for Radiation Safety in Israel

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Topics: Radiation (Physics) , Safety , Emergencies

Research Papers

Development of Kinetic Models for the Long-Term Corrosion Behavior of Candidate Alloys for the Canadian SCWR

G. Steeves, W. Cook

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031001. doi: https://doi.org/10.1115/1.4035549

Abstract

View articletitled, Development of Kinetic Models for the Long-Term Corrosion Behavior of Candidate Alloys for the Canadian SCWR

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Topics: Alloys , Corrosion , Metals , Oxidation , Supercritical water reactors , Temperature , Weight (Mass) , Water , Fuels , Cladding systems (Building)

Thermo-Economic Performance of a Cogeneration Medium–Small Modular Nuclear Reactor Plant in Canada

Gaoming Ge, Tomohiko Ikegawa, Koji Nishida, Carey J. Simonson

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031002. doi: https://doi.org/10.1115/1.4035335

Abstract

View articletitled, Thermo-Economic Performance of a Cogeneration Medium–Small Modular Nuclear Reactor Plant in Canada

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Topics: Boilers , Combined heat and power , Heat , High temperature , Electric power generation , Natural gas , Steam , Carbon

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

X. Gaus-Liu, A. Miassoedov

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031003. doi: https://doi.org/10.1115/1.4035853

Abstract

View articletitled, Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

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Topics: Boundary-value problems , Cooling , Heat flux , Heat transfer , Temperature , Vessels , Geometry , Insulation , Water

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031004. doi: https://doi.org/10.1115/1.4035934

Abstract

View articletitled, The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

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Topics: Boundary-value problems , Reflection , Trajectories (Physics) , Geometry , Rotation

Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load

Emiliya Georgieva, Yavor Dinkov, Kostadin Ivanov

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031005. doi: https://doi.org/10.1115/1.4035550

Abstract

View articletitled, Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load

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Topics: Coolants , Flow (Dynamics) , Fuels , Manufacturing , Pressure , Simulation , Steam , Stress , Temperature , Transients (Dynamics)

Mass Optimization of a Supercritical CO₂ Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor

Kurt E. Harris, Kevin J. Schillo, Yayu M. Hew, Akansha Kumar, Steven D. Howe

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031006. doi: https://doi.org/10.1115/1.4035974

Abstract

View articletitled, Mass Optimization of a Supercritical CO2 Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor

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Topics: Brayton cycle , Compressors , Cycles , Fluids , Heat exchangers , Nuclear fission , Power conversion systems , Pressure , Supercritical carbon dioxide , Temperature

An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor

A. K. Srivastava, R. Chouhan, A. Borgohain, S. S. Jana, N. K. Maheshwari, D. S. Pilkhwal, A. Rama Rao, K. N. Hareendhran, S. Chowdhury, K. B. Modi, S. K. Raut, S. C. Parida

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031007. doi: https://doi.org/10.1115/1.4036027

Abstract

View articletitled, An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor

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Topics: Boundary-value problems , Breeder reactors , Computational fluid dynamics , Flow (Dynamics) , Simulation , Steady state , Temperature , Transients (Dynamics) , Fluids , Instrumentation

Technical Brief

A Review of Safety Analysis Philosophies for Nuclear Reactors

A. S. Schneider, N. Yair

ASME J of Nuclear Rad Sci. July 2017, 3(3): 034501. doi: https://doi.org/10.1115/1.4035565

Abstract

View articletitled, A Review of Safety Analysis Philosophies for Nuclear Reactors

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Topics: Nuclear reactors , Safety , Design , Accidents , Defense industry

MCNP Simulation of In-Core Dose Rates for an Offline CANDU^® Reactor

Jordan G. Gilbert, Scott Nokleby, Ed Waller

ASME J of Nuclear Rad Sci. July 2017, 3(3): 034502. doi: https://doi.org/10.1115/1.4036354

Abstract

View articletitled, MCNP Simulation of In-Core Dose Rates for an Offline CANDU® Reactor

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Topics: Fuels , Inspection , Pressure , Simulation , Robotics , Particulate matter , Fittings

Guest Editorial

Special Section: Selected Papers from the 28th Conference of the Nuclear Societies in Israel

Special Section Papers

Novel Genetic Algorithms for Loading Pattern Optimization Using State-of-the-Art Operators and a Simple Test Case

Nozzle Geometry Effect on Stratified Layer Erosion by Vertical Turbulent Jet

Integrated Blast Resistance Model of Nuclear Power Plant Auxiliary Facilities

Impact From Fly Ash as Additive to Concrete on the Radiation Exposure in Dwellings

Minimizing Ionizing Radiation Exposure in Invasive Cardiology Safety Training for Medical Doctors

A Study of the External Exposure Decay Curves as a Function of Several Clinical Parameters for Patients Treated With Therapeutic ¹³¹I

Cesium and Strontium Immobilization in Portland Cement Pastes Blended With Pozzolanic Additives

How Thick Should Cover Layer be for Radioactive Waste Disposal Facility? The Case of the Yamin Plain, Israel

Evaluation of Hydrogel Technologies for the Decontamination of ¹³⁷Cs From Building Material Surfaces

Fission Track Detection Using Automated Microscopy

Detection of Combined n/γ Fission Signatures Induced by an Epithermal Neutron Source

Optimization of a Multiline Neutron Source Based on a ²³²Th Filter

Ni Interlayer to Improve Low-Pressure Diffusion Bonding of 316L SS Press Fit Tube-to-Tubesheet Joints for Coiled Tube Gas Heaters

Resistance Improvement of Aluminum Surface to Corrosion Through Reactions With Fluoride Ions

Safety Improvement to Israel Research Reactor 2 by Increasing the Robustness of Equipment to Ground Acceleration

An Improved Method for Estimating the Dose to the Lens of the Eye Using Hp(10) and Hp(0.07) Measurements

Effective Dose Reduction in Lateral Lumbar Spine Diagnostic Radiography Using X-Ray Tube Heel Effect

The Standard for Radiation Protection of the IAEC as a Model for a Revision of the Legal Framework for Radiation Safety in Israel

Research Papers

Development of Kinetic Models for the Long-Term Corrosion Behavior of Candidate Alloys for the Canadian SCWR

Thermo-Economic Performance of a Cogeneration Medium–Small Modular Nuclear Reactor Plant in Canada

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load

Mass Optimization of a Supercritical CO₂ Brayton Cycle Power Conversion System for a Mars Surface Fission Power Reactor

An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor

Technical Brief

A Review of Safety Analysis Philosophies for Nuclear Reactors

MCNP Simulation of In-Core Dose Rates for an Offline CANDU^® Reactor

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