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

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Volume 2, Issue 2

April 2016

ISSN 2332-8983

EISSN 2332-8975

In Memoriam

In Memoriam: Jan Kysela

Martin Ruscak, Thomas Schulenberg, Igor Pioro, Michal Kostal

ASME J of Nuclear Rad Sci. April 2016, 2(2): 020101. doi: https://doi.org/10.1115/1.4032548

Extract

View articletitled, In Memoriam: Jan Kysela

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Topics: Water , Water chemistry , Chemistry , Corrosion , Energy generation , Nuclear research , Pressurized water reactors , Supercritical water reactors , Biomedicine , Boiling water reactors

Research Papers

Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

Eric C. Forrest, Sarah M. Don, Lin-Wen Hu, Jacopo Buongiorno, Thomas J. McKrell

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021001. doi: https://doi.org/10.1115/1.4031503

Abstract

View articletitled, Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

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Topics: Boiling , Bubbles , Flow (Dynamics) , Forced convection , Heat flux , Pressure , Temperature , Temperature measurement , Water , Flux (Metallurgy)

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

Jun Wang, Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Michael L. Corradini, Guanghui Su, Suizheng Qiu

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002. doi: https://doi.org/10.1115/1.4031842

Abstract

View articletitled, The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

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Topics: Accidents , Flow (Dynamics) , Temperature , Vessels , Melting , Hydrogen

Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

Ikuo Kinoshita, Toshihide Torige, Minoru Yamada

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021003. doi: https://doi.org/10.1115/1.4031377

Abstract

View articletitled, Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

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Topics: Friction , Fuel rods , Porosity , Uncertainty , Uncertainty quantification , Geometry , Flow (Dynamics)

Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited

Graham A. Ferrier, Mohsen Farahani, Joseph Metzler, Paul K. Chan, Emily C. Corcoran

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021004. doi: https://doi.org/10.1115/1.4031620

Abstract

View articletitled, Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited

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Topics: Coatings , Graphite , Coating processes , Fuels , Siloxanes

Supercritical Oxidation of Boiler Tube Materials

Satu Tuurna, Sanni Yli-Olli, Sami Penttilä, Pertti Auerkari, Xiao Huang

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021005. doi: https://doi.org/10.1115/1.4031338

Abstract

View articletitled, Supercritical Oxidation of Boiler Tube Materials

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Topics: Alloys , Oxidation , Steam , Weight (Mass) , Temperature , Boiler tubes , Power stations , Pressure

Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In-Core Components of a Gen-IV SCWR

Robert J. Klassen, Heygaan Rajakumar

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021006. doi: https://doi.org/10.1115/1.4031015

Abstract

View articletitled, Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In-Core Components of a Gen-IV SCWR

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Topics: Alloys , Irradiation (Radiation exposure) , Damage , Supercritical water reactors , Hardening

Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

O. S. Bakai, V. M. Boriskin, A. M. Dovbnya, S. V. Dyuldya, D. A. Guzonas

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021007. doi: https://doi.org/10.1115/1.4031126

Abstract

View articletitled, Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

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Topics: Alloys , Corrosion , Irradiation (Radiation exposure) , Temperature , Water , Zirconium , Electrons , Chemistry , Oxidation , Coolants

Oxidation Behavior of Austenitic Stainless Steel 316L and 310S in Air and Supercritical Water

Majid Nezakat, Hamed Akhiani, Sami Penttilä, Jerzy Szpunar

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021008. doi: https://doi.org/10.1115/1.4031817

Abstract

View articletitled, Oxidation Behavior of Austenitic Stainless Steel 316L and 310S in Air and Supercritical Water

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Topics: Oxidation , Stainless steel , Water , Weight (Mass) , Alloys

Microstructural Effects on the Oxidation Behavior of Alloy 800HT in Supercritical Water

Hamed Akhiani, Majid Nezakat, Sami Penttilä, Jerzy Szpunar

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021009. doi: https://doi.org/10.1115/1.4031036

Abstract

View articletitled, Microstructural Effects on the Oxidation Behavior of Alloy 800HT in Supercritical Water

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Topics: Alloys , Grain size , Oxidation , Water , Grain boundaries

Fission Product Release Under Supercritical Water-Cooled Reactor Conditions

D. Guzonas, L. Qiu, S. Livingstone, S. Rousseau

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021010. doi: https://doi.org/10.1115/1.4031381

Abstract

View articletitled, Fission Product Release Under Supercritical Water-Cooled Reactor Conditions

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Topics: Nuclear fission , Temperature , Water , Supercritical water reactors , Fuels

Performance of Chemical Vapor Deposition and Plasma Spray-Coated Stainless Steel 310 in Supercritical Water

Xiao Huang, Q. Yang, Dave Guzonas

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021011. doi: https://doi.org/10.1115/1.4031198

Abstract

View articletitled, Performance of Chemical Vapor Deposition and Plasma Spray-Coated Stainless Steel 310 in Supercritical Water

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Topics: Chemical vapor deposition , Coatings , Plasmas (Ionized gases) , Sprays , Stainless steel , Testing , Water , Weight (Mass) , Coating processes

A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle

M. Rohde, J. W. R. Peeters, A. Pucciarelli, A. Kiss, Y. F. Rao, E. N. Onder, P. Muehlbauer, A. Batta, M. Hartig, V. Chatoorgoon, R. Thiele, D. Chang, S. Tavoularis, D. Novog, D. McClure, M. Gradecka, K. Takase

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021012. doi: https://doi.org/10.1115/1.4031949

Abstract

View articletitled, A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle

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Topics: Flow (Dynamics) , Heat transfer , Reynolds-averaged Navier–Stokes equations , Rods , Simulation , Temperature , Turbulence , Wall temperature , Water , Fuel rods

Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

Rudi Van Nieuwenhove

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021013. doi: https://doi.org/10.1115/1.4030798

Abstract

View articletitled, Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

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Topics: Fuels , Instrumentation , Irradiation (Radiation exposure) , Pressurized water reactors , Temperature , Testing , Water , Corrosion , Boiling water reactors , Heating

Radiolysis of Supercritical Water at 400°C: A Sensitivity Study of the Density Dependence of the Yield of Hydrated Electrons on the (eaq−+eaq−) Reaction Rate Constant

Sunuchakan Sanguanmith, Jintana Meesungnoen, David A. Guzonas, Craig R. Stuart, Jean-Paul Jay-Gerin

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021014. doi: https://doi.org/10.1115/1.4031013

Abstract

View articletitled, Radiolysis of Supercritical Water at 400°C: A Sensitivity Study of the Density Dependence of the Yield of Hydrated Electrons on the (eaq−+eaq−) Reaction Rate Constant

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Topics: Density , Electrons , Simulation , Water , Temperature , Reaction rate constants

Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian-SCWR Supercell

Haykel Raouafi, Guy Marleau

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021015. doi: https://doi.org/10.1115/1.4030895

Abstract

View articletitled, Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian-SCWR Supercell

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Topics: Boron , Supercritical water reactors , Coolants , Fuels , Density , Simulation , Rods

Implicit Model Equation for Hydraulic Resistance and Heat Transfer including Wall Roughness

Eckart Laurien

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021016. doi: https://doi.org/10.1115/1.4031948

Abstract

View articletitled, Implicit Model Equation for Hydraulic Resistance and Heat Transfer including Wall Roughness

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Topics: Friction , Heat transfer , Pipes , Surface roughness , Temperature , Turbulence , Shear stress

Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Jason R. Sharpe, Adriaan Buijs, Jeremy Pencer

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021017. doi: https://doi.org/10.1115/1.4031074

Abstract

View articletitled, Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

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Topics: Design , Fuels , Isotopes , Nuclear fission , Optimization , Spent nuclear fuels , Supercritical water reactors , Uncertainty , Density , Nuclides

Overview on Fusion Nuclear Technology Experimental Testing

Slavomir Entler, Jan Kysela

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021018. doi: https://doi.org/10.1115/1.4031942

Abstract

View articletitled, Overview on Fusion Nuclear Technology Experimental Testing

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Topics: Corrosion , Irradiation (Radiation exposure) , Neutrons , Testing , Eutectic alloys , Nuclear reactors , Cycles , Fusion reactors , Heat flux

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

Abstract

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

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

Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model

Andrea Querol, Sergio Gallardo, Gumersindo Verdú

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021020. doi: https://doi.org/10.1115/1.4031016

Abstract

View articletitled, Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model

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Topics: Cladding systems (Building) , Coolants , Delays , Flow (Dynamics) , Pressure , Temperature , Thermocouples , Transients (Dynamics) , Steady state , Secondary cells

Steady-State Radiolysis of Supercritical Water: Model Predictions and Validation

V. Subramanian, J. M. Joseph, H. Subramanian, J. J. Noël, D. A. Guzonas, J. C. Wren

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021021. doi: https://doi.org/10.1115/1.4031199

Abstract

View articletitled, Steady-State Radiolysis of Supercritical Water: Model Predictions and Validation

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Topics: Water , Temperature , Steady state , Water vapor

Iodine Benchmarks in the SARNET Network of Excellence

Tim Haste, Mirco Di Giuli, Gunter Weber, Sebastian Weber

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021022. doi: https://doi.org/10.1115/1.4031652

Abstract

View articletitled, Iodine Benchmarks in the SARNET Network of Excellence

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Topics: Chemistry , Circuits , Containment , Uncertainty , Aerosols , Flow (Dynamics) , Steel , Water , Thermal hydraulics , Modeling

Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code

A. Abarca, R. Miró, G. Verdú, J. A. Bermejo

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021023. doi: https://doi.org/10.1115/1.4031660

Abstract

View articletitled, Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code

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Topics: Fluctuations (Physics) , Noise (Sound) , Oscillations , Pressurized water reactors , Simulation , Steady state , Temperature , Nuclear power stations , Neutrons

Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH-LOCA-1

Alexander Vasiliev, Juri Stuckert

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021024. doi: https://doi.org/10.1115/1.4031815

Abstract

View articletitled, Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH-LOCA-1

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Topics: Accidents , Cladding systems (Building) , Hydrogen , Modeling , Temperature , Water , Thermomechanics , Rods , Steam , Heat

Technical Brief

TRICO II Core Inventory Calculation and its Radiological Consequence Analyses

J. L. Muswema, G. B. Ekoko, J. K.-K. Lobo, V. M. Lukanda, E. K. Boafo

ASME J of Nuclear Rad Sci. April 2016, 2(2): 024501. doi: https://doi.org/10.1115/1.4031772

Abstract

View articletitled, TRICO II Core Inventory Calculation and its Radiological Consequence Analyses

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Topics: Accidents , Damage , Fuels , Meteorology , Radioisotopes , Safety , Radiation (Physics) , Plumes (Fluid dynamics)

In Memoriam

In Memoriam: Jan Kysela

Research Papers

Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited

Supercritical Oxidation of Boiler Tube Materials

Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In-Core Components of a Gen-IV SCWR

Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

Oxidation Behavior of Austenitic Stainless Steel 316L and 310S in Air and Supercritical Water

Microstructural Effects on the Oxidation Behavior of Alloy 800HT in Supercritical Water

Fission Product Release Under Supercritical Water-Cooled Reactor Conditions

Performance of Chemical Vapor Deposition and Plasma Spray-Coated Stainless Steel 310 in Supercritical Water

A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle

Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions

Radiolysis of Supercritical Water at 400°C: A Sensitivity Study of the Density Dependence of the Yield of Hydrated Electrons on the (eaq−+eaq−) Reaction Rate Constant

Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian-SCWR Supercell

Implicit Model Equation for Hydraulic Resistance and Heat Transfer including Wall Roughness

Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Overview on Fusion Nuclear Technology Experimental Testing

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

Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model

Steady-State Radiolysis of Supercritical Water: Model Predictions and Validation

Iodine Benchmarks in the SARNET Network of Excellence

Analysis of Thermal-Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code

Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH-LOCA-1

Technical Brief

TRICO II Core Inventory Calculation and its Radiological Consequence Analyses

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