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International Journal of Nuclear Energy

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主页: http://www.hindawi.com/journals/ijne/

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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

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

Vigilija Cidzikien？,Vaidot？ Jakimavi？iūt？-Maselien？,Rasel？ Girg？dien？,Jonas Ma？eika,Rimantas Petro？ius

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

O. I. Yaskiv,V. M. Fedirko

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

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

J. Rosales,A. Mu？oz,C. García,L. García,C. Brayner,J. Pérez,A. Abánades

Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant

Bryan Poulson

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

Ayah Elshahat,Timothy Abram,Judith Hohorst,Chris Allison

Sensitivity Analysis of the TRIGA IPR-R1 Reactor Models Using the MCNP Code

C. A. M. Silva,J. A. D. Salomé,B. T. Guerra,C. Pereira,A. L. Costa,M. A. F. Veloso,M. A. B. C. Menezes,H. M. Dalle

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

G. G. Kulikov,A. N. Shmelev,V. A. Apse

Thermal Analysis of ZPPR High Pu Content Stored Fuel

Charles W. Solbrig,Chad L. Pope,Jason P. Andrus

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

Molecular Dynamics Study of Hydrogen in α-Zirconium

Ravi Kiran Siripurapu,Barbara Szpunar,Jerzy A. Szpunar

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

Rickard R. Shen,Bartek Kaplan,P？l Efsing

RELAP5 Analyses of ROSA/LSTF Experiments on AM Measures during PWR Vessel Bottom Small-Break LOCAs with Gas Inflow

Takeshi Takeda

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

Deepthi Chandramouli,Shripad T. Revankar

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

Thermal Conductivity of Uranium Nitride and Carbide

B. Szpunar,J. A. Szpunar

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

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

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

O. V. Marchenko,S. V. Solomin

Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics

Ahmed E. Aboanber

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

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

Amir Zacarias Mesquita,Rogério Rivail Rodrigues

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