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Volume 149

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Nuclear Technology / Volume 149 / Number 1

January 2005

Table of Contents

Nuclear Technology / Volume 149 / Number 2

February 2005

Table of Contents

Nuclear Technology / Volume 149 / Number 3

March 2005

Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities

Marko Maucec, Bogdan Glumac

Nuclear Technology / Volume 149 / Number 1 / Pages 1-13

January 2005

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Price:$30.00

A New Apparatus for Determination of the Free Volume of a Fuel Rod Using the Double Expansion Method

Lionel Desgranges, Marie-Hèlene Faure, Alain Thouroude

Nuclear Technology / Volume 149 / Number 1 / Pages 14-21

January 2005

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The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design

Ser Gi Hong, Ehud Greenspan, Yeong Il Kim

Nuclear Technology / Volume 149 / Number 1 / Pages 22-48

January 2005

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Computational Fluid Dynamics Prediction of Grid Spacer Thermal-Hydraulic Performance with Comparison to Experimental Results

Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter

Nuclear Technology / Volume 149 / Number 1 / Pages 49-61

January 2005

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Numerical Optimization for the Design of a Spacer Grid with Mixing Vanes in a Pressurized Water Reactor Fuel Assembly

Kwang-Yong Kim, Jun-Woo Seo

Nuclear Technology / Volume 149 / Number 1 / Pages 62-70

January 2005

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Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code

Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, Young-Min Kwon, Yong-Bum Lee

Nuclear Technology / Volume 149 / Number 1 / Pages 71-87

January 2005

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Experimental Research on In-Tube Condensation Under Steady-State and Transient Conditions

Ali Tanrikut, Orhan Yesin

Nuclear Technology / Volume 149 / Number 1 / Pages 88-100

January 2005

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Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach

Iraci Martinez Gonçalves, Daniel K. S. Ting, Paulo Brasko Ferreira, Belle R. Upadhyaya

Nuclear Technology / Volume 149 / Number 1 / Pages 101-109

January 2005

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Performance-Based (Risk-Informed) Regulation: A Regulatory Perspective

N. Prasad Kadambi

Nuclear Technology / Volume 149 / Number 1 / Pages 110-121

January 2005

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Review and Research of the Neutron Source Multiplication Method in Nuclear Critical Safety

Yong-Qian Shi, Qing-Fu Zhu, He Tao

Nuclear Technology / Volume 149 / Number 1 / Pages 122-127

January 2005

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The Impact of Uncertainties on the Performance of Passive Systems

Lorenzo P. Pagani, George E. Apostolakis, Pavel Hejzlar

Nuclear Technology / Volume 149 / Number 2 / Pages 129-140

February 2005

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Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel

Mikio Sakai, Toshihiro Yamamoto, Minoru Murazaki, Yoshinori Miyoshi

Nuclear Technology / Volume 149 / Number 2 / Pages 141-149

February 2005

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Dynamics of Critical Dedicated Cores for Minor Actinide Transmutation

S. Massara, J. Tommasi, M. Vanier, O. Köberl

Nuclear Technology / Volume 149 / Number 2 / Pages 150-174

February 2005

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Impact of Pin-by-Pin Thermal-Hydraulic Feedback Modeling on Steady-State Core Characteristics

Akio Yamamoto, Tsutomu Ikeno

Nuclear Technology / Volume 149 / Number 2 / Pages 175-188

February 2005

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Thermal Interaction Between Molten Metal Jet and Sodium Pool: Effect of Principal Factors Governing Fragmentation of the Jet

Satoshi Nishimura, Izumi Kinoshita, Ken-Ichiro Sugiyama, Nobuyuki Ueda

Nuclear Technology / Volume 149 / Number 2 / Pages 189-199

February 2005

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Integral Test and Engineering Analysis of Coolant Depletion During a Large-Break Loss-of-Coolant Accident

Yong Soo Kim, Chang Hwan Park, Byoung Uhn Bae, Goon Cherl Park, Kune Yull Suh, Un Chul Lee

Nuclear Technology / Volume 149 / Number 2 / Pages 200-216

February 2005

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Development of a New Aqueous Process for Nuclear Fuel Reprocessing: Hot Tests on the Recovery of U and Pu from a Nitric Acid Solution of Spent LWR Fuel

Yuezhou Wei, Tsuyoshi Arai, Harutaka Hoshi, Mikio Kumagai, Aimé Bruggeman, Patrick Goethals

Nuclear Technology / Volume 149 / Number 2 / Pages 217-231

February 2005

Format:

Price:$30.00
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