American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 143 / Number 3

Volume 143

Number 3

Using Point Reactor Models and Genetic Algorithms for On-Line Global Xenon Estimation in Nuclear Reactors

Tunc Aldemir, Giancarlo Torri, Marzio Marseguerra, Enrico Zio, Jeffrey A. Borkowski

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 247-255

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3414

Analysis of Burnup and Economic Potential of Alternative Fuel Materials in Thermal Reactors

Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 256-269

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3415

Maintenance Cycle Extension in the IRIS Advanced Light Water Reactor Plant Design

Mark R. Galvin, Neil E. Todreas, Larry E. Conway

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 270-280

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3416

Safety Analysis of Fast Reactor Core with Uranium-Free Fuel for Actinide Transmutation

Igor Krivitski, Mikhail Vorotyntsev, Valentin Pyshin, Ludmila Korobeinikova

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 281-289

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3417

Step Complexity Measure for Emergency Operating Procedures - Determining Weighting Factors

Jinkyun Park, Wondea Jung, Jaewhan Kim, Jaejoo Ha

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 290-308

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3418

Mobility and Criticality of Plutonium in a Repository

Bernhard Kienzler, Andreas Loida, Werner Maschek, Andrei Rineiski

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 309-321

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3419

Radionuclide Transport in a Multiple and Parallel Fractured System

Chih-Tien Liu, Hund-Der Yeh

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 322-334

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3420

The Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Purified and Crude Sodium Bentonites in Carbonate Buffered Solution

Mitsuo Manaka

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 335-346

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3421

Development of Creep Constitutive Equation for Low-Alloy Steel

Kwang J. Jeong, Joon Lim, Il S. Hwang, Hee D. Kim, Martin M. Pilch, Tze Y. Chu

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 347-357

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT03-A3422

Monte Carlo Modeling of the Portuguese Research Reactor Core and Comparison with Experimental Measurements

Ana C. Fernandes, Isabel C. Gonçalves, Nuno P. Barradas, António J. Ramalho

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 358-363

Technical Note / Fission Reactors / dx.doi.org/10.13182/NT03-A3423

Power Profile Evaluation of the JCO Precipitation Vessel Based on the Record of the Gamma-Ray Monitor

Kotaro Tonoike, Takemi Nakamura, Yuichi Yamane, Yoshinori Miyoshi

Nuclear Technology / Volume 143 / Number 3 / September 2003 / Pages 364-372

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT03-A3424

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use