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Journal Articles

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.

Paper No: NERS-20-1167

DOI: https://doi.org/10.1115/1.4052591

Published Online: January 11, 2022

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Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps

Journal Articles

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.

Paper No: NERS-21-1043

DOI: https://doi.org/10.1115/1.4052589

Published Online: October 29, 2021

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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization

Journal Articles

Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

Boris Haranki, Ufuk Dilek

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024501.

Paper No: NERS-19-1159

DOI: https://doi.org/10.1115/1.4051363

Published Online: October 19, 2021

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Topics: ASTM International, Concretes, Design, Flow (Dynamics), Nuclear construction, Pumps, Stability

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.

Paper No: NERS-20-1059

DOI: https://doi.org/10.1115/1.4051364

Published Online: August 12, 2021

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Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.

Paper No: NERS-20-1080

DOI: https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels

Journal Articles

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Jeremy Bittan, Clement Bore, Joel Guidez

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041301.

Paper No: NERS-20-1079

DOI: https://doi.org/10.1115/1.4048991

Published Online: April 16, 2021

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Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps

Journal Articles

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.

Paper No: NERS-20-1157

DOI: https://doi.org/10.1115/1.4050207

Published Online: March 10, 2021

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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors

Journal Articles

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Terry Price, Zack Taylor, Ondrej Chvala

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041302.

Paper No: NERS-19-1107

DOI: https://doi.org/10.1115/1.4046258

Published Online: June 3, 2020

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Topics: Bubbles, Fuels, Molten salt reactors, Porosity, Pressure, Nuclear fission, Flow (Dynamics), Pumps

Journal Articles

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

Edward Shitsi, Emmanuel K. Boafo, Felix Ameyaw, H. C. Odoi

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801.

Paper No: NERS-19-1117

DOI: https://doi.org/10.1115/1.4045803

Published Online: March 9, 2020

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Topics: Failure, Feedwater, High pressure (Physics), Pumps, Safety, Valves, Nuclear power stations

Journal Articles

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107.

Paper No: NERS-19-1028

DOI: https://doi.org/10.1115/1.4045034

Published Online: January 29, 2020

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Topics: Accidents, Coolants, Cooling, Diesel engines, Emergencies, Flow (Dynamics), Hazards, Heat, Leakage, Pressure

Journal Articles

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.

Paper No: NERS-19-1001

DOI: https://doi.org/10.1115/1.4044847

Published Online: November 29, 2019

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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models

Journal Articles

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

S. P. Saraswat, D. Ray, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. October 2019, 5(4): 042202.

Paper No: NERS-18-1030

DOI: https://doi.org/10.1115/1.4042707

Published Online: July 19, 2019

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Topics: Accidents, Coolants, Cooling systems, Design, Heat, Heat sinks, Modeling, Plasmas (Ionized gases), Pressure, Sprays

Journal Articles

The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island

Chongzhi Wu, Jindong Zhang, Zongkui Wang, Zengkui Zhang, Shenqing Fu

ASME J of Nuclear Rad Sci. April 2019, 5(2): 025501.

Paper No: NERS-17-1172

DOI: https://doi.org/10.1115/1.4042221

Published Online: March 15, 2019

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Topics: Metals, Nuclear power, Spectroscopy, Welding, Pumps, Nozzles, Construction, Pipes, Heat

Journal Articles

Precautions at Fukushima That Would Have Suppressed the Accident Severity

Kenji Iino, Ritsuo Yoshioka, Masao Fuchigami, Masayuki Nakao

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031007.

Paper No: NERS-17-1051

DOI: https://doi.org/10.1115/1.4039343

Published Online: May 16, 2018

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Topics: Accidents, Earthquakes, Fukushima nuclear disaster, Japan, 2011, Seawater, Tsunamis, Water, Heat, Pumps, Electricity (Physics), Evaporation

Journal Articles

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.

Paper No: NERS-16-1133

DOI: https://doi.org/10.1115/1.4039000

Published Online: March 5, 2018

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

Journal Articles

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.

Paper No: NERS-16-1114

DOI: https://doi.org/10.1115/1.4038062

Published Online: March 5, 2018

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

Journal Articles

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.

Paper No: NERS-16-1132

DOI: https://doi.org/10.1115/1.4035550

Published Online: May 25, 2017

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

Journal Articles

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.

Paper No: NERS-15-1106

DOI: https://doi.org/10.1115/1.4035046

Published Online: December 20, 2016

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

Journal Articles

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.

Paper No: NERS-15-1170

DOI: https://doi.org/10.1115/1.4034477

Published Online: December 20, 2016

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

Journal Articles

Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test

Manuel Raqué, Thomas Schulenberg, Tobias Zeiger

ASME J of Nuclear Rad Sci. January 2016, 2(1): 011005.

Paper No: NERS-15-1052

DOI: https://doi.org/10.1115/1.4030917

Published Online: December 9, 2015

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Topics: Accidents, Coolants, Design, Fuels, Pressure, Safety, Temperature, Flow (Dynamics), Failure, Heat

Journal citation

NARROW

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Utilization of Self-Consolidating Concrete Technology for Large Placements in New Nuclear Construction: A Study on Self-Consolidating Concrete Stability and Constructability

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

The Necessity to Reexamine Key Component Material With Spectrometry Analysis in the Nuclear Island

Precautions at Fukushima That Would Have Suppressed the Accident Severity

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

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

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

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

Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures

Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test

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