American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 169

Volume 169

Number 1 | Number 2 | Number 3

Number 1

Interpretation of the Phébus FPT0 and FPT1 Circuit Results Using the SOPHAEROS/ASTEC V1 Module

A. Bujan, B. Tóth, A. Bieliauskas, R. Zeyen, C. Housiadas

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 1-17

Technical Paper / Reactor Safety

Importance Ranking of Parameters Affecting Reactor Dynamics Using the Taguchi Method

Luv Sharma, Tunc Aldemir, Robert Parker

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 18-33

Technical Paper / Reactor Safety

RELAP5 Analysis of Two-Phase Decompression and Rarefaction Wave Propagation Under a Temperature Gradient

Nathan Lafferty, Victor Ransom, Martin Lopez De Bertodano

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 34-49

Technical Paper / Thermal Hydraulics

Analysis of a Coupled Blowdown from Both RPV and BOP with RELAP5-3D/K for a Limiting FWLB of an ABWR for Containment Design

Thomas K. S. Liang, Show-Chyuan Chiang, Chung-Yu Yang, Liang-Che Dai

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 50-60

Technical Paper / Thermal Hydraulics

Enhanced Thermal Conductivity for LWR Fuel

Jamil A. Khan, Travis W. Knight, Sujan B. Pakala, Wei Jiang, Ruixian Fang, James S. Tulenko

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 61-72

Technical Paper / Thermal Hydraulics

Three-Dimensional X-Ray CT Image of an Irradiated FBR Fuel Assembly

Kozo Katsuyama, Koji Maeda, Tsuyoshi Nagamine, Hirotaka Furuya

Nuclear Technology / Volume 169 / Number 1 / January 2010 / Pages 73-80

Technical Paper / Radiation Measurements and Instrumentation

Number 2

Benchmark Study on Fuel Bundle Degradation in the Phebus FPT2 Test Using State-of-the-Art Severe Accident Analysis Codes

B. Tóth, A. Bieliauskas, G. Bandini, J. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 81-96

Technical Paper / Reactor Saftey

Modeling Molten Fuel-Moderator Interactions for the CANDU Flow Blockage Accident

Aya Diab, Michael Corradini

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 97-113

Technical Paper / Thermal Hydraulics

Long-Term Validation of the Molten Fuel-Moderator Interactions Model

Aya Diab, Michael Corradini, Carl Martin

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 114-125

Technical Paper / Thermal Hydraulics

Analysis of Flow Instability for OTSG Using Frequency Domain Control Theory

Suxia Hou, Fuyu Zhao, Yun Tai, Liu Cheng

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 126-133

Technical Paper / Thermal Hydraulics

Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code

Kwi-Seok Ha, Hae-Yong Jeong, Chungho Cho, Young-Min Kwon, Yong-Bum Lee, Dohee Hahn

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 134-142

Technical Paper / Thermal Hydraulics

Loading Capacities for Uranium, Plutonium, and Neptunium in High Caustic Nuclear Waste Storage Tanks Containing Selected Sorbents

Lawrence N. Oji, William R. Wilmarth, David T. Hobbs

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 143-149

Technical Paper / Radioactive Waste Management and Disposal

A Container Based on Polymer Composite Materials for the Ultimate Disposal of Spent Nuclear Fuel and Radioactive Waste

H. W. Bonin, J. R. Van Tine, V. T. Bui

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 150-179

Technical Paper / Radioactive Waste Management and Disposal

Estimating Surface Facility Throughput During the Preclosure Emplacement Period at Yucca Mountain

Leah Spradley, Mark Abkowitz, James H. Clarke

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 180-194

Technical Paper / Radioactive Waste Management and Disposal

Analytical and Experimental Investigation of Recent Challenges to Neutron Attenuation and the Relationship with Criticality Analyses

Stanley E. Turner, Thomas G. Haynes III

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 195-203

Technical Note / Radiation Protection

Number 3

A Study on Dynamic Characteristics of Plate-Fin Recuperator in High-Temperature Gas-Cooled Reactor Closed Cycle

Ming Ding, Xiaoyong Yang, Jie Wang

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 205-217

Technical Paper / Fission Reactors

LWR Severe Accident Simulation Fission Product Behavior in FPT2 Experiment

N. Girault, L. Bosland, J. Dienstbier, R. Dubourg, C. Fiche

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 218-238

Technical Paper / Reactor Safety

Triggered Steam Explosions with Corium Melts of Various Compositions in a Narrow Interaction Vessel in the TROI Facility

J. H. Kim, B. T. Min, I. K. Park, S. W. Hong

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 239-251

Technical Paper / Thermal Hydraulics

Critical Discretization Issues in 3-D SN Simulations Relevant to Dosimetry and Medical Physics

Ahmad K. Al-Basheer, Glenn E. Sjoden, Monica Ghita

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 252-262

Technical Paper / Radiation Protection

Dissolution of Zircaloy-2-Clad UO2 Commercial Reactor Fuel

G. F. Kessinger, M. C. Thompson

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 263-270

Technical Paper / Reprocessing

Raman and SEM/EDS Characterization of Cr-Doped Natural Diamond Particles

Adrián E. Méndez Torres, Mark Antonio Prelas, Louis M. Ross, Jr., Tushar K. Ghosh

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 271-278

Technical Paper / Materials for Nuclear Systems

Industrial-Scale Production of 99mTc Generators for Clinical Use Based on Zirconium Molybdate Gel

M. Ghannadi Maragheh, M. R. Davarpanah, M. Fazlali, M. Kazemi Boudani, B. Pour Emadi, S. Attar Nosrati

Nuclear Technology / Volume 169 / Number 3 / March 2010 / Pages 279-284

Technical Paper / Radioisotopes

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement