Volume 2 Issue 3 | ASME J. of Nuclear Rad Sci.

Topics: Accidents , Coolants , Critical heat flux , Fuel rods , Fuels , Heat transfer , Irradiation (Radiation exposure) , Pressurized water reactors , Simulation , Transients (Dynamics)

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Kaichao Sun, Lin-Wen Hu, Charles Forsberg

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031003. doi: https://doi.org/10.1115/1.4032873

Abstract

View articletitled, Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

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Topics: Coolants , Design , Fuels , Nuclear fuel cycle , Safety , Rods , Particulate matter , Control systems , High temperature

Experimental and Numerical Study of Supercritical Carbon Dioxide Flow Through Valves

Haomin Yuan, Mark Anderson

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031004. doi: https://doi.org/10.1115/1.4032640

Abstract

View articletitled, Experimental and Numerical Study of Supercritical Carbon Dioxide Flow Through Valves

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Topics: Flow (Dynamics) , Valves , Supercritical carbon dioxide , Pressure

On Some Relevant Effects in the Simulation of Flow Stability With Fluids at Supercritical Pressure

Walter Ambrosini

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031005. doi: https://doi.org/10.1115/1.4032595

Abstract

View articletitled, On Some Relevant Effects in the Simulation of Flow Stability With Fluids at Supercritical Pressure

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Topics: Computational fluid dynamics , Diffusion (Physics) , Flow (Dynamics) , Fluids , Heating , Pressure , Stability , Heat capacity , Errors

An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions

Amir Ali, Edward D. Blandford

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031006. doi: https://doi.org/10.1115/1.4032439

Abstract

View articletitled, An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions

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Topics: Accidents , Containment , Coolants , Fibers , Flow (Dynamics) , Particulate matter , Stability , Testing , Water , Pressurized water reactors

European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

Radek Novotný, Přemysl Janík, Aki Toivonen, Anna Ruiz, Zoltan Szaraz, Lefu Zhang, Jan Siegl, Petr Haušild, Sami Penttilä, Jan Macák

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031007. doi: https://doi.org/10.1115/1.4032871

Abstract

View articletitled, European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

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Topics: Corrosion , Corrosion resistance , Finishes , Flow (Dynamics) , Fuels , Oxygen , Stainless steel , Supercritical water reactors , Temperature , Water

European Project “Supercritical Water Reactor–Fuel Qualification Test”: Results of Fuel Pin Mock-up Tests

Radek Novotný, Dirk Visser, Theo Timke, Aleš Vojáček, Otakar Frýbort, Jan Siegl, Petr Haušild, Jan Macák

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031008. doi: https://doi.org/10.1115/1.4032636

Abstract

View articletitled, European Project “Supercritical Water Reactor–Fuel Qualification Test”: Results of Fuel Pin Mock-up Tests

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Topics: Fuels , Pressure

Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

Pertti Auerkari, Sanni Yli-Olli, Sami Penttilä, Satu Tuurna, Rami Pohja

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031009. doi: https://doi.org/10.1115/1.4032783

Abstract

View articletitled, Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

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Topics: High temperature , Oxidation , Steel , Temperature , Corrosion , Thermal power stations , Power stations , Stress , Modeling

HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity

Hiroyuki Sato, Xing L. Yan, Junya Sumita, Atsuhiko Terada, Yukio Tachibana

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031010. doi: https://doi.org/10.1115/1.4032480

Abstract

View articletitled, HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity

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Topics: Combined heat and power , Design , Gas turbines , Heat , Helium , Hydrogen , Safety , Temperature , Very high temperature reactors

A Study of Acoustic Wave Resonance in Water-Filled Tubes With Different Wall Thicknesses and Materials

Alireza Mokhtari, Vijay Chatoorgoon

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031011. doi: https://doi.org/10.1115/1.4032781

Abstract

View articletitled, A Study of Acoustic Wave Resonance in Water-Filled Tubes With Different Wall Thicknesses and Materials

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Topics: Resonance , Computational fluid dynamics , Damping

On Calculating Heat Transfer and Pressure Drop of Supercritical-Pressure Coolants

Vladimir A. Kurganov, Yuri A. Zeigarnik, Irina V. Maslakova

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031012. doi: https://doi.org/10.1115/1.4032440

Abstract

View articletitled, On Calculating Heat Transfer and Pressure Drop of Supercritical-Pressure Coolants

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Topics: Coolants , Flow (Dynamics) , Heat transfer , Water

An Experiment of Natural Circulation Flow and Heat Transfer With Supercritical Water in Parallel Channels

Yuzhou Chen, Chunsheng Yang, Minfu Zhao, Keming Bi, Kaiwen Du

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031013. doi: https://doi.org/10.1115/1.4032779

Abstract

View articletitled, An Experiment of Natural Circulation Flow and Heat Transfer With Supercritical Water in Parallel Channels

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Topics: Flow (Dynamics) , Heat transfer , Water , Water temperature , Heat flux , Temperature , Pressure

Analysis and Assessment of a Gas Turbine-Modular Helium Reactor for Nuclear Desalination

Farrukh Khalid, Ibrahim Dincer, Marc A. Rosen

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031014. doi: https://doi.org/10.1115/1.4032508

Abstract

View articletitled, Analysis and Assessment of a Gas Turbine-Modular Helium Reactor for Nuclear Desalination

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Topics: Electric power generation , Exergy , Helium , Seawater , Steam turbines , Temperature , Turbines , Gas turbines

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

Malwina Gradecka, Roman Thiele, Henryk Anglart

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031015. doi: https://doi.org/10.1115/1.4032635

Abstract

View articletitled, Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

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Topics: Computational fluid dynamics , Flow (Dynamics) , Fuel rods , Heat transfer , Rods , Temperature , Water , Geometry , Boundary-value problems , Fluids

Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes

Amjad Farah, Glenn Harvel, Igor Pioro

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031016. doi: https://doi.org/10.1115/1.4032642

Abstract

View articletitled, Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes

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Topics: Computational fluid dynamics , Fluids , Heat transfer , Temperature , Turbulence , Wall temperature , Water , Pressure , Heat flux , Heat

Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes

Xianliang Lei, Huixiong Li, Weiqiang Zhang

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031017. doi: https://doi.org/10.1115/1.4032872

Abstract

View articletitled, Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes

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Topics: Flux (Metallurgy) , Heat , Heat transfer , Numerical analysis , Pressure , Supercritical fluids , Temperature , Turbulence , Wall temperature , Heat flux

Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

Zafar Ullah Koreshi, Hamda Khan

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031018. doi: https://doi.org/10.1115/1.4032702

Abstract

View articletitled, Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

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Topics: Explosives , Genetic algorithms , Neutrons , Optimization , Diffusion (Physics) , Water , Design , Signals , Sensors

Direct Numerical Simulation of Heated Turbulent Pipe Flow at Supercritical Pressure

Xu Chu, Eckart Laurien

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031019. doi: https://doi.org/10.1115/1.4032479

Abstract

View articletitled, Direct Numerical Simulation of Heated Turbulent Pipe Flow at Supercritical Pressure

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Topics: Flow (Dynamics) , Pipes , Pressure , Turbulence , Simulation , Heat transfer , Pipe flow , Computer simulation , Buoyancy , Wall temperature

Design and Implementation of an Automated Gamma Probe for Jet Boring Uranium Mining

Kasmet T. Niyongabo, Scott B. Nokleby

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031020. doi: https://doi.org/10.1115/1.4032634

Abstract

View articletitled, Design and Implementation of an Automated Gamma Probe for Jet Boring Uranium Mining

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Topics: Design , Probes , Sensors , Drills (Tools) , Testing , Lakes , Drilling

Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model

Michio Murase, Yoichi Utanohara, Takayoshi Kusunoki, Dirk Lucas, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031021. doi: https://doi.org/10.1115/1.4033629

Abstract

View articletitled, Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model

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Topics: Computation , Flow (Dynamics) , Pipes , Simulation , Surges , Uncertainty , Water , Computer simulation , Floods

Technical Brief

U233 Data Evaluation for Criticality Study

Mohammad Alrwashdeh, Wang Kan

ASME J of Nuclear Rad Sci. July 2016, 2(3): 034501. doi: https://doi.org/10.1115/1.4032814

Abstract

View articletitled, U233 Data Evaluation for Criticality Study

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Topics: Bayes methods , Computers , Cross section (Physics) , Databases , Fittings , Thermal energy , Nuclear fission , Computer software , Neutrons

Book Review

Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.

DUMITRU SERGHIUTA

ASME J of Nuclear Rad Sci. July 2016, 2(3): 036501. doi: https://doi.org/10.1115/1.4033479

Extract

View articletitled, <strong>Global Neutron Calculations,</strong> by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.

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Topics: Neutrons , Nuclear engineering , Physics , Transport theory

Research Papers

Effects of Decay Heat Distribution on Water Temperature in a Spent Fuel Pit and Prediction Errors With a One-Region Model

COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Experimental and Numerical Study of Supercritical Carbon Dioxide Flow Through Valves

On Some Relevant Effects in the Simulation of Flow Stability With Fluids at Supercritical Pressure

An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions

European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

European Project “Supercritical Water Reactor–Fuel Qualification Test”: Results of Fuel Pin Mock-up Tests

Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity

A Study of Acoustic Wave Resonance in Water-Filled Tubes With Different Wall Thicknesses and Materials

On Calculating Heat Transfer and Pressure Drop of Supercritical-Pressure Coolants

An Experiment of Natural Circulation Flow and Heat Transfer With Supercritical Water in Parallel Channels

Analysis and Assessment of a Gas Turbine-Modular Helium Reactor for Nuclear Desalination

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat-Transfer Applications in Vertical Bare Tubes

Numerical Analysis on Heat-Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes

Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm

Direct Numerical Simulation of Heated Turbulent Pipe Flow at Supercritical Pressure

Design and Implementation of an Automated Gamma Probe for Jet Boring Uranium Mining

Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10-Scale Model

Technical Brief

U233 Data Evaluation for Criticality Study

Book Review

Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978-1-68108-027-7, ISBN978-1-68108-028-4.

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