Volume 3 Issue 1 | ASME J. of Nuclear Rad Sci.

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Editorial

Editorial Greeting to Journal Readers 2017

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2017, 3(1): 010201. doi: https://doi.org/10.1115/1.4035065

Extract

View articletitled, Editorial Greeting to Journal Readers 2017

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Topics: Nuclear engineering , Radiation (Physics) , China , Safety

List of Reviewers for 2016

ASME J of Nuclear Rad Sci. January 2017, 3(1): 010202. doi: https://doi.org/10.1115/1.4035080

Extract

View articletitled, List of Reviewers for 2016

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Topics: Nuclear engineering , Radiation (Physics)

Review Article

60 Years in Motion: Short History of Nuclear Engineering Division

Jovica Riznic, Romney Duffey

ASME J of Nuclear Rad Sci. January 2017, 3(1): 010801. doi: https://doi.org/10.1115/1.4035177

Abstract

View articletitled, 60 Years in Motion: Short History of Nuclear Engineering Division

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Research Papers

Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel

Matthew C. Morrison, Kenneth J. Bateman

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011001. doi: https://doi.org/10.1115/1.4032999

Abstract

View articletitled, Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel

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Topics: Containers , Storage , Switches , Vacuum pumps , Cooling

Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop

Chaofei Jiang, Wenxi Tian, Suizheng Qiu, Guanghui Su

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011002. doi: https://doi.org/10.1115/1.4035046

Abstract

View articletitled, Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop

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Topics: Accidents , Coolants , Flow (Dynamics) , Fuels , Heat , Pressure , Safety , Supercritical water reactors , Transients (Dynamics) , Water

Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

Donald M. McEligot, Richard W. Johnson

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011003. doi: https://doi.org/10.1115/1.4035047

Abstract

View articletitled, Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

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Topics: Flow (Dynamics) , Friction , Turbulence , Computational fluid dynamics , Laminar flow , Ducts , Reynolds number , Geometry

Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications

Rusi P. Taleyarkhan, Jeffrey A. Webster, Anthony Sansone, Brian C. Archambault, Randall Reames, Colin D. West

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011004. doi: https://doi.org/10.1115/1.4034975

Abstract

View articletitled, Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications

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Topics: Cavitation , Fluids , Glass , Radiation (Physics) , Testing , Water , Safety , Pressure , Tension , Nuclear engineering

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005. doi: https://doi.org/10.1115/1.4033813

Abstract

View articletitled, Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

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Topics: High temperature , Neutron flux , Rods , Fuels , Design , Temperature , Computational methods

Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds

Daniel LaBrier, Amir Ali, Kerry J. Howe, Edward D. Blandford

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011006. doi: https://doi.org/10.1115/1.4034569

Abstract

View articletitled, Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds

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Topics: Aluminum , Corrosion , Epoxy adhesives , Epoxy resins , Fibers , Metals , Temperature , Chemistry , Water , Glass reinforced plastics

Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures

Belle R. Upadhyaya, Chaitanya Mehta, J. Wesley Hines, Victor B. Lollar, Duygu Bayram

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011007. doi: https://doi.org/10.1115/1.4034477

Abstract

View articletitled, Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures

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Topics: Engines , Flow (Dynamics) , Motors , Pumps , Pressure , Small modular reactors , Valves

A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks

Tian Chen, Antoine Joly, Rong Pan, Ping Ji, Guofei Chen

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011008. doi: https://doi.org/10.1115/1.4034974

Abstract

View articletitled, A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks

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Topics: Floods , Nuclear power stations , Seas , Shorelines , Simulation , Storms , Surges , Waves , Tides , Water

Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

Alberto Sáez-Maderuelo, Dolores Gómez-Briceño, César Maffiotte

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011009. doi: https://doi.org/10.1115/1.4032780

Abstract

View articletitled, Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

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Topics: Pressure , Temperature , Water , Stainless steel , Oxidation , Stress corrosion cracking

Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors

Foad Mehdi Zadeh, Stéphane Etienne, Alberto Teyssedou

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011010. doi: https://doi.org/10.1115/1.4032874

Abstract

View articletitled, Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors

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Topics: Flow (Dynamics) , Nuclear reactors , Simulation , Computational fluid dynamics , Temperature

Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle

Jawad Haroon, Leslie Kicka, Subhramanyu Mohapatra, Eleodor Nichita, Peter Schwanke

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011011. doi: https://doi.org/10.1115/1.4034571

Abstract

View articletitled, Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle

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Topics: Coolants , Density , Fuels , Heavy water reactors , Temperature

Influence of Pleat Deformation on Pressure Drop for a High-Efficiency Particulate Air Filter: A Small-Scale Experimental Approach

S. Bourrous, L. Bouilloux, P. Nerisson, D. Thomas, J. C. Appert-Collin

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011012. doi: https://doi.org/10.1115/1.4034711

Abstract

View articletitled, Influence of Pleat Deformation on Pressure Drop for a High-Efficiency Particulate Air Filter: A Small-Scale Experimental Approach

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Topics: Deformation , Filters , Filtration , Pressure drop , Particulate matter , Geometry

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011013. doi: https://doi.org/10.1115/1.4033812

Abstract

View articletitled, Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

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Topics: Evaluation methods , High temperature , Temperature , Design , Cycles , Temperature distribution , Physics , Very high temperature reactors

SMR Fuel Cycle Optimization Using LWROpt

Keith E. Ottinger, G. Ivan Maldonado

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011014. doi: https://doi.org/10.1115/1.4034573

Abstract

View articletitled, SMR Fuel Cycle Optimization Using LWROpt

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Topics: Carbon reinforced plastics , Optimization , Nuclear fuel cycle , Cycles , Fuels , Pressurized water reactors

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015. doi: https://doi.org/10.1115/1.4034478

Abstract

View articletitled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

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Topics: Heat flux , Nucleate boiling , Pressurized water reactors , Rods , Safety , Scram , Spacetime , Thermal hydraulics , Transients (Dynamics) , Temperature profiles

Full-Scope Probabilistic Safety Assessment of Balakovo Unit 1 in Russia

Vladimir Morozov, Gennady Tokmachev, Rostislav Lutsuk, Sergey Kopylov

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011016. doi: https://doi.org/10.1115/1.4033087

Abstract

View articletitled, Full-Scope Probabilistic Safety Assessment of Balakovo Unit 1 in Russia

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Topics: Damage , Fire , Floods , Fuels , Hazards , Probabilistic safety assessment , Safety , Licensing , Nuclear power stations , Accidents

Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

A. Gad-Briggs, P. Pilidis

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011017. doi: https://doi.org/10.1115/1.4033398

Abstract

View articletitled, Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

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Topics: Compressors , Cycles , Helium , Pressure , Sensitivity analysis , Temperature , Turbines , Thermal efficiency , Gas turbines

Innovation of Irradiation Equipment at the LVR-15 Nuclear Research Reactor

Zdena Lahodová, Witolda Soukupová, Michal Koleška, Jaroslav Ernest, Jelena Zmítková

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011018. doi: https://doi.org/10.1115/1.4032599

Abstract

View articletitled, Innovation of Irradiation Equipment at the LVR-15 Nuclear Research Reactor

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Topics: Irradiation (Radiation exposure) , Nuclear research , Neutrons , Radiation (Physics) , Heating , Temperature , Design , Fluence (Radiation measurement)

The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor

Martin Schulc, Michal Košťál, Davit Harutyunyan, Marie Švadlenková, Vojtěch Rypar, Ján Milčák, Antonín Kolros

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011019. doi: https://doi.org/10.1115/1.4034568

Abstract

View articletitled, The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor

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Topics: Iron , Neutrons , Power density , Steel , Fuels , Pins (Engineering) , Sensors

Backbone: A Multiphysics Framework for Coupling Nuclear Codes Based on CORBA and MPI

Yu Liu, Michael Nishimura, Marat Seydaliev, Markus Piro

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011020. doi: https://doi.org/10.1115/1.4034061

Abstract

View articletitled, Backbone: A Multiphysics Framework for Coupling Nuclear Codes Based on CORBA and MPI

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Topics: Control equipment , Design , Errors , Fuels , Safety , Simulation , Computer programming , Nuclear fission , Computer software , Computer programming languages

Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011021. doi: https://doi.org/10.1115/1.4034479

Abstract

View articletitled, Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants

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Topics: Cycles , Pressure , Temperature , Compressors , Turbines , Helium

Technical Brief

Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

Jia Yang, Rongyong Zhang

ASME J of Nuclear Rad Sci. January 2017, 3(1): 014501. doi: https://doi.org/10.1115/1.4035285

Abstract

View articletitled, Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

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Topics: Condensers (steam plant) , Cooling , Optimization , Sensitivity analysis , Steam turbines , Design , Nuclear power stations , Tariffs , Cooling towers , Pipes

Validation of the Onsite Used Operational Code Against Burnup Measurement

Michal Koleška, Michal Šunka, Jaroslav Ernest

ASME J of Nuclear Rad Sci. January 2017, 3(1): 014502. doi: https://doi.org/10.1115/1.4034570

Abstract

View articletitled, Validation of the Onsite Used Operational Code Against Burnup Measurement

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Topics: Fuels , Nuclear fission , Nuclear fuel cycle , Manufacturing , Thermography , Spent nuclear fuels

Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

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

ASME J of Nuclear Rad Sci. January 2017, 3(1): 014503. doi: https://doi.org/10.1115/1.4034680

Abstract

View articletitled, Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

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Topics: Accidents , Coolants , Flow (Dynamics) , Heat , Helium , Vessels , Safety , Cooling systems , Design , Temperature

Editorial

Editorial Greeting to Journal Readers 2017

List of Reviewers for 2016

Review Article

60 Years in Motion: Short History of Nuclear Engineering Division

Research Papers

Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel

Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop

Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications

Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor

Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds

Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures

A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks

Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors

Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle

Influence of Pleat Deformation on Pressure Drop for a High-Efficiency Particulate Air Filter: A Small-Scale Experimental Approach

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

SMR Fuel Cycle Optimization Using LWROpt

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Full-Scope Probabilistic Safety Assessment of Balakovo Unit 1 in Russia

Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants

Innovation of Irradiation Equipment at the LVR-15 Nuclear Research Reactor

The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor

Backbone: A Multiphysics Framework for Coupling Nuclear Codes Based on CORBA and MPI

Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants

Technical Brief

Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis

Validation of the Onsite Used Operational Code Against Burnup Measurement

Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code

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