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Research Article
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oa

Experimental Measurements of Drop Size Distributions in 30 mm Diameter Annular Centrifugal Contactor with 30% TBP-Nitric Acid Biphasic System
Shekhar Kumar, U. Kamachi Mudali,

First published: 23 June 2013
Research Article
Open Access

oa

Study of Thorium Fuel Cycles for Light Water Reactor VBER-150
Daniel Evelio Milian Lorenzo, Daniel Milian Pérez, Lorena Pilar Rodríguez García, Jesús Salomón Llanes, Carlos Alberto Brayner de Oliveira Lira, Manuel Cadavid Rodríguez, Carlos Rafael García Hernández,

First published: 23 December 2013
Research Article
Open Access

oa

Economic Assessment of Russian Nuclear Strategies on the Basis of Fast Breeder Reactors
O. V. Marchenko, S. V. Solomin,

First published: 09 October 2013
Research Article
Open Access

oa

Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics
Ahmed E. Aboanber,

First published: 13 August 2013
Research Article
Open Access

oa

A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries
Hirofumi Ohashi, Hiroyuki Sato, Minoru Goto, Xing Yan, Junya Sumita, Yujiro Tazawa, Yasunobu Nomoto, Jun Aihara, Yoshitomo Inaba, Yuji Fukaya, Hiroki Noguchi, Yoshiyuki Imai, Yukio Tachibana,

First published: 26 December 2013
Research Article
Open Access

oa

Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators
Amir Zacarias Mesquita, Rogério Rivail Rodrigues,

First published: 02 June 2013
Research Article
Open Access

oa

Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code
N. H. Badrun, M. H. Altaf, M. A. Motalab, M. S. Mahmood, M. J. H. Khan,

First published: 09 December 2014
Research Article
Open Access

oa

Thermal Conductivity of Uranium Nitride and Carbide
B. Szpunar, J. A. Szpunar,

First published: 01 September 2014
Research Article
Open Access

oa

Analysis of Loss of Flow Events on Brazilian Multipurpose Reactor Using the Relap5 Code
Humberto V. Soares, Ivan D. Aronne, Antonella L. Costa, Claubia Pereira, Maria Auxiliadora F. Veloso,

First published: 03 June 2014
Research Article
Open Access

oa

Assessment of Tritium Activity in Groundwater at the Nuclear Objects Sites in Lithuania
Vigilija Cidzikienė, Vaidotė Jakimavičiūtė-Maselienė, Raselė Girgždienė, Jonas Mažeika, Rimantas Petrošius,

First published: 12 March 2014
Research Article
Open Access

oa

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX
J. Rosales, A. Muñoz, C. García, L. García, C. Brayner, J. Pérez, A. Abánades,

First published: 17 September 2014
Research Article
Open Access

oa

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction
G. G. Kulikov, A. N. Shmelev, V. A. Apse,

First published: 16 October 2014
Research Article
Open Access

oa

Thermal Analysis of ZPPR High Pu Content Stored Fuel
Charles W. Solbrig, Chad L. Pope, Jason P. Andrus,

First published: 17 September 2014
Research Article
Open Access

oa

Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM
Ayah Elshahat, Timothy Abram, Judith Hohorst, Chris Allison,

First published: 16 December 2014
Review Article
Open Access

oa

Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant
Bryan Poulson,

First published: 13 October 2014
Research Article
Open Access

oa

Experimental and Theoretical Investigation of Three Alloy 690 Mockup Components: Base Metal and Welding Induced Changes
Rickard R. Shen, Bartek Kaplan, Pål Efsing,

First published: 03 August 2014
Research Article
Open Access

oa

A Parametric Study of the Impact of the Cooling Water Site Specific Conditions on the Efficiency of a Pressurized Water Reactor Nuclear Power Plant
Mohamed M. A. Ibrahim, Mohamed R. Badawy,

First published: 28 August 2014
Research Article
Open Access

oa

Oxidation/Corrosion Behaviour of ODS Ferritic/Martensitic Steels in Pb Melt at Elevated Temperature
O. I. Yaskiv, V. M. Fedirko,

First published: 03 March 2014
Research Article
Open Access

oa

Development of Thermal Models and Analysis of UO₂-BeO Fuel during a Loss of Coolant Accident
Deepthi Chandramouli, Shripad T. Revankar,

First published: 26 August 2014
Research Article
Open Access

oa

The Impact of Climate Changes on the Thermal Performance of a Proposed Pressurized Water Reactor: Nuclear-Power Plant
Said M. A. Ibrahim, Mohamed M. A. Ibrahim, Sami. I. Attia,

First published: 10 April 2014

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International Journal of Nuclear Energy

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All International Journal of Nuclear Energy Articles

oa

Experimental Measurements of Drop Size Distributions in 30 mm Diameter Annular Centrifugal Contactor with 30% TBP-Nitric Acid Biphasic System

oa

Study of Thorium Fuel Cycles for Light Water Reactor VBER-150

oa

Economic Assessment of Russian Nuclear Strategies on the Basis of Fast Breeder Reactors

oa

Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics

oa

A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries

oa

Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators

oa

Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code

oa

Thermal Conductivity of Uranium Nitride and Carbide

oa

Analysis of Loss of Flow Events on Brazilian Multipurpose Reactor Using the Relap5 Code

oa

Assessment of Tritium Activity in Groundwater at the Nuclear Objects Sites in Lithuania

oa

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

oa

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

oa

Thermal Analysis of ZPPR High Pu Content Stored Fuel

oa

Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM

oa

Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant

oa

Experimental and Theoretical Investigation of Three Alloy 690 Mockup Components: Base Metal and Welding Induced Changes

oa

A Parametric Study of the Impact of the Cooling Water Site Specific Conditions on the Efficiency of a Pressurized Water Reactor Nuclear Power Plant

oa

Oxidation/Corrosion Behaviour of ODS Ferritic/Martensitic Steels in Pb Melt at Elevated Temperature

oa

Development of Thermal Models and Analysis of UO₂-BeO Fuel during a Loss of Coolant Accident

oa

The Impact of Climate Changes on the Thermal Performance of a Proposed Pressurized Water Reactor: Nuclear-Power Plant

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oa Experimental Measurements of Drop Size Distributions in 30 mm Diameter Annular Centrifugal Contactor with 30% TBP-Nitric Acid Biphasic System

oa Study of Thorium Fuel Cycles for Light Water Reactor VBER-150

oa Economic Assessment of Russian Nuclear Strategies on the Basis of Fast Breeder Reactors

oa Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics

oa A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries

oa Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators

oa Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code

oa Thermal Conductivity of Uranium Nitride and Carbide

oa Analysis of Loss of Flow Events on Brazilian Multipurpose Reactor Using the Relap5 Code

oa Assessment of Tritium Activity in Groundwater at the Nuclear Objects Sites in Lithuania

oa Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

oa Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

oa Thermal Analysis of ZPPR High Pu Content Stored Fuel

oa Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM

oa Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant

oa Experimental and Theoretical Investigation of Three Alloy 690 Mockup Components: Base Metal and Welding Induced Changes

oa A Parametric Study of the Impact of the Cooling Water Site Specific Conditions on the Efficiency of a Pressurized Water Reactor Nuclear Power Plant

oa Oxidation/Corrosion Behaviour of ODS Ferritic/Martensitic Steels in Pb Melt at Elevated Temperature

oa Development of Thermal Models and Analysis of UO2-BeO Fuel during a Loss of Coolant Accident

oa The Impact of Climate Changes on the Thermal Performance of a Proposed Pressurized Water Reactor: Nuclear-Power Plant

oa

Experimental Measurements of Drop Size Distributions in 30 mm Diameter Annular Centrifugal Contactor with 30% TBP-Nitric Acid Biphasic System

oa

Study of Thorium Fuel Cycles for Light Water Reactor VBER-150

oa

Economic Assessment of Russian Nuclear Strategies on the Basis of Fast Breeder Reactors

oa

Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics

oa

A Small-Sized HTGR System Design for Multiple Heat Applications for Developing Countries

oa

Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod Simulators

oa

Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code

oa

Thermal Conductivity of Uranium Nitride and Carbide

oa

Analysis of Loss of Flow Events on Brazilian Multipurpose Reactor Using the Relap5 Code

oa

Assessment of Tritium Activity in Groundwater at the Nuclear Objects Sites in Lithuania

oa

Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

oa

Improving Nuclear Safety of Fast Reactors by Slowing Down Fission Chain Reaction

oa

Thermal Analysis of ZPPR High Pu Content Stored Fuel

oa

Simulation of the Westinghouse AP1000 Response to SBLOCA Using RELAP/SCDAPSIM

oa

Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant

oa

Experimental and Theoretical Investigation of Three Alloy 690 Mockup Components: Base Metal and Welding Induced Changes

oa

A Parametric Study of the Impact of the Cooling Water Site Specific Conditions on the Efficiency of a Pressurized Water Reactor Nuclear Power Plant

oa

Oxidation/Corrosion Behaviour of ODS Ferritic/Martensitic Steels in Pb Melt at Elevated Temperature

oa

Development of Thermal Models and Analysis of UO₂-BeO Fuel during a Loss of Coolant Accident

oa

The Impact of Climate Changes on the Thermal Performance of a Proposed Pressurized Water Reactor: Nuclear-Power Plant