ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT10-A9339

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 / dx.doi.org/10.13182/NT10-A9340

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 / dx.doi.org/10.13182/NT169-3

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 / dx.doi.org/10.13182/NT10-A9342

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 / dx.doi.org/10.13182/NT10-A9343

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 / dx.doi.org/10.13182/NT10-A9344

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 / dx.doi.org/10.13182/NT10-A9354

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 / dx.doi.org/10.13182/NT10-A9355

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 / dx.doi.org/10.13182/NT10-A9356

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 / dx.doi.org/10.13182/NT10-A9357

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 / dx.doi.org/10.13182/NT10-A9358

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 / dx.doi.org/10.13182/NT10-A9359

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 / dx.doi.org/10.13182/NT10-A9360

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 / dx.doi.org/10.13182/NT10-A9361

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 / dx.doi.org/10.13182/NT10-A9362

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 / dx.doi.org/10.13182/NT10-A9374

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 / dx.doi.org/10.13182/NT10-A9375

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 / dx.doi.org/10.13182/NT169-239

Critical Discretization Issues in 3-D S_N 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 / dx.doi.org/10.13182/NT10-A9377

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 / dx.doi.org/10.13182/NT10-A9378

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 / dx.doi.org/10.13182/NT10-A9379

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 / dx.doi.org/10.13182/NT10-A9380