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Volume 156

Number 2

Developing a Tool for Simulating the Behavior of Axial Flux Difference During Power Reduction for Maanshan Pressurized Water Reactor Units

Jau-Tyne Yeh, Ta-Lun Sung, J. Y. Shiue

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 125-132

Technical Paper / Fission Reactors

Simulation of a PWR Reactor Vessel Level Indicating System During Station Blackout with MELCOR 1.8.5

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 133-139

Technical Paper / Fission Reactors

Off-Gas Source Estimation for Boiling Water Reactors Under Various Operation Conditions

Masato Takahashi

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 140-149

Technical Paper / Fission Reactors

Failure Mode and Effect Analysis Application for the Safety and Reliability Analysis of a Thermal-Hydraulic Passive System

Luciano Burgazzi

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 150-158

Technical Paper / Reactor Safety

Enhancement of Safety Analysis Capability for a CANDU-6 Reactor Using RELAP-CANDU/SCAN Coupled Code System

Manwoong Kim, Hyun-Koon Kim, Hho-Jung Kim, Su Hyon Hwang, In Seob Hong, Chang Hyo Kim

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 159-167

Technical Paper / Reactor Safety

Genetic Algorithm to Optimize the UO2/Gd2O3 Fuel Pin Designs in a Pressurized Water Reactor

Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 168-179

Technical Paper / Fuel Cycle and Management

Genetic Algorithm Application for Burnable Poison Placement in PWRs with Optimized UO2/Gd2O3 Fuel Pin Configurations

Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 180-190

Technical Paper / Fuel Cycle and Management

Assessment of S/R5/MOD3.3 Models of Stratified Molten Pool and Debris-to-Vessel Contact Resistance by TMI-2 Lower-Head Creep Rupture Analyses

Sang Lung Chan

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 191-212

Technical Paper / Thermal Hydraulics

Properties of Titanium-Nitride for High-Level Waste Packaging Enhancement

C. C. Scheffing, K. Jagannadham, M.-S. Yim, M. A. Bourham, J. C. Farmer, J. J. Haslam, S. D. Day, D. V. Fix, N. Y. Yang

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 213-221

Technical Paper / Radioactive Waste Management and Disposal

Numerical Study of Nuclide Migration in a Nonuniform Horizontal Flow Field of a High-Level Radioactive Waste Repository with Multiple Canisters

Doo-Hyun Lim

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 222-245

Technical Paper / Radioactive Waste Management and Disposal

 
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