American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 149 / Number 1

Volume 149

Number 1

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

Marko Maucec, Bogdan Glumac

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 1-13

Technical Paper / Reactor Safety

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 / January 2005 / Pages 14-21

Technical Paper / Fuel Cycle and Management

The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design

Ser Gi Hong, Ehud Greenspan, Yeong Il Kim

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 22-48

Technical Paper / Fuel Cycle and Management

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 / January 2005 / Pages 49-61

Technical Paper / Thermal Hydraulics

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 / January 2005 / Pages 62-70

Technical Paper / Thermal Hydraulics

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 / January 2005 / Pages 71-87

Technical Paper / Thermal Hydraulics

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

Ali Tanrikut, Orhan Yesin

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 88-100

Technical Paper / Thermal Hydraulics

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 / January 2005 / Pages 101-109

Technical Paper / Nuclear Plant Operations and Control

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

N. Prasad Kadambi

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 110-121

Technical Paper / Miscellaneous

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 / January 2005 / Pages 122-127

Technical Note / Reactor Safety

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement