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Volume 143

Number 1

Safety System Design Concept and Performance Evaluation for a Long Operating Cycle Simplified Boiling Water Reactor

Kenji Arai, Seijiro Suzuki, Mikihide Nakamaru, Hideaki Heki

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3393

Rapid-L Operator-Free Fast Reactor Concept Without Any Control Rods

Mitsuru Kambe, Hirokazu Tsunoda, Kaichiro Mishima, Takamichi Iwamura

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 11-21

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3394

Performance of Thorium-Based Mixed-Oxide Fuels for the Consumption of Plutonium in Current and Advanced Reactors

Kevan D. Weaver, J. Stephen Herring

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 22-36

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3395

Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection

Horst-Michael Prasser, Gerhard Grunwald, Thomas Höhne, Sören Kliem, Ulrich Rohde, Frank-Peter Weiss

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 37-56

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3396

Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus During LBLOCA Reflood Phase with a Direct Vessel Injection Mode

Tae-Soon Kwon, Byong-Jo Yun, Dong-Jin Euh, In-Cheol Chu, Chul-Hwa Song

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 57-64

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3397

Experimental Study on the Performance of the Passive Safety Injection in an IIST

Chin-Jang Chang, Chien-Hsiung Lee, Wen-Tang Hong, Lance L. C. Wang

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 65-76

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3398

Stability of Natural-Circulation-Cooled Boiling Water Reactors During Startup: Experimental Results

Annalisa Manera, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 77-88

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3399

Critical Power Correlation for Axially Uniformly Heated Tight-Lattice Bundles

Masatoshi Kureta, Hajime Akimoto

Nuclear Technology / Volume 143 / Number 1 / July 2003 / Pages 89-100

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT143-89

 

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