全部 标题 作者
关键词 摘要

OALib Journal期刊
ISSN: 2333-9721
费用：99美元
投递稿件

为什么选择我们？ >>
- 开源期刊
- 同行审议
- 快速出刊
- 终身存储
- 免费检索
- 免费推广
- 更多...
- 搜索引擎

International Journal of Nuclear Energy

ISSN Print:

ISSN Online:

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

分享:




Go

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

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

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

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

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

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

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

Takeshi Takeda

Thermal Conductivity of Uranium Nitride and Carbide

B. Szpunar,J. A. Szpunar

Predicting and Preventing Flow Accelerated Corrosion in Nuclear Power Plant

Bryan Poulson

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

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

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

Molecular Dynamics Study of Hydrogen in α-Zirconium

Ravi Kiran Siripurapu,Barbara Szpunar,Jerzy A. Szpunar

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

Thermal Analysis of ZPPR High Pu Content Stored Fuel

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

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

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

Ayah Elshahat,Timothy Abram,Judith Hohorst,Chris Allison

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

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

Amir Zacarias Mesquita,Rogério Rivail Rodrigues

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

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

Generalized and Stability Rational Functions for Dynamic Systems of Reactor Kinetics

Ahmed E. Aboanber

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

O. V. Marchenko,S. V. Solomin

Go




©2008-2020 OALib, Inc | Public user content licensed CC-BY 4.0 unless otherwise specified. OALib ISSN Online: 2333-9721 OALib ISSN Print: 2333-9705