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Volume 129

Number 1

First In-Pile Experimental Results of High-Plutonium-Content Oxide Fuel for Plutonium Burning in Fast Reactors

Emmanuelle Picard, Jean Noirot, Raymond L. Moss, Helmut Plitz, Karl Richter, Jacques Rouault

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 1-12

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-2

Code Development and Assessment for Reactor Outage Thermal-Hydraulic and Safety Analysis - Midloop Operation with Loss of Residual Heat Removal

Thomas K. S. Liang, Fu-Kuang Ko

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 13-25

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3042

A Nodal Kinetics and Thermohydraulics Analysis (NOKTA) Code for Analyzing Rod-Ejection Accidents and Other Transients in Nuclear Power Reactor Cores

Sadi Kaya, Hasbi Yavuz

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 26-35

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3043

An Evaluation of Emergency Operator Actions by an Experimental SGTR Event at the IIST Facility and a Comparison of Mihama-2 SGTR Event Record

Tay-Jian Liu, Chien-Hsiung Lee, Ching-Chuan Yao, Show-Chyuan Chiang

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 36-50

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3044

Full-Load-Rejection Design Analysis for the Lungmen Advanced Boiling Water Reactor Using RETRAN

Jan-Ru Tang, Lainsu Kao, Jong-Rong Wang, Ruey-Yng Yuann

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 51-68

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3045

Suppression of Vapor Explosions in a Water-Molten-Tin System by Augmentation of the Void Fraction

Michael K. Meeks, Michael C. Baker, Riccardo Bonazza

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 69-81

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3046

Simulation of Two Loss-of-Flow Transients in a VVER-1000 Nuclear Power Plant with RELAP5/MOD3.2 System Code

Yassin A. Hassan, Dionisie R. Moscalu

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 82-92

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3047

Nonphosphate Degradation Products of Tributyl Phosphate and Their Reactivities in Purex Media Under Extreme Conditions

Yoshikazu Tashiro, Ryuji Kodama, Hiroshi Sugai, Katsuhiko Suzuki, Shingo Matsuoka

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 93-100

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT00-A3048

Long-Term Leaching Experiments of Full-Scale Cemented Waste Forms: Experiments and Modeling

Bernhard Kienzler, Peter Vejmelka, Horst-Jürgen Herbert, Herbert Meyer, Corinna Altenhein-Haese

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 101-118

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3049

Radiation Chemical Effects in the Near Field of a Final Disposal Site - I: Radiolytic Products Formed in Concentrated NaCl Solutions

M. Kelm, E. Bohnert

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 119-122

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3050

Radiation Chemical Effects in the Near Field of a Final Disposal Site - II: Simulation of the Radiolytic Processes in Concentrated NaCl Solutions

M. Kelm, E. Bohnert

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 123-130

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3051

The Self-Ignition Temperatures of Bitumen Mixtures Containing Transition Metal Nitrates

Ken Okada, Masao Nomura, Yasuhiko Fujii

Nuclear Technology / Volume 129 / Number 1 / January 2000 / Pages 131-139

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3052

 

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