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Volume 139

Number 1

Passive System Reliability Analysis: A Study on the Isolation Condenser

Luciano Burgazzi

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 3-9

Technical Paper

Severe Accident Related Research and Development at Forschungszentrum Karlsruhe for Present and Future Needs

Werner Scholtyssek, Gerhard Heusener, Fritz Hofmann, Helmut Plitz

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 10-20

Technical Paper

The Model of the IBR-2 Pulsed Reactor Dynamics and Investigation of Pulse Energy Stabilization

Alexander K. Popov, Juri N. Pepyolyshev, Eugene A. Bondarchenko

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 21-29

Technical Paper

Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor

Hyung-Joon Ahn, Jae-Hun Lee, Young-Seok Bang, Hho-Jung Kim

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 30-35

Technical Note

General Safety Criteria for the Korean Next Generation Reactor

Jae-Hun Lee, Woong-Sik Kim, Young Gill Yune, Jae-Seong Lee

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 36-41

Technical Note

Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System

Cheol Shin Lee, Chan Eok Park, Chul Jin Choi, Jong Tae Seo

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 42-49

Technical Note

Definition and Analysis of an Experimental Benchmark on Shutdown Rod Worths in LEU-HTR Configurations

Rakesh Chawla, Om Parkash Joneja, Marc Rosselet, Tony Williams

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 50-60

Technical Paper / Reactor Safety

A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs

Antonino Romano, Neil E. Todreas

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 61-71

Technical Paper / Fuel Cycle and Management

Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids

Wang Kee In, Dong Seok Oh, Tae Hyun Chun

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 72-79

Technical Paper / Thermal Hydraulics

Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant

Sedat Goluoglu, R. T. Primm III

Nuclear Technology / Volume 139 / Number 1 / July 2002 / Pages 80-88

Technical Note / Criticality of Nuclear Materials

 
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