American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 149

Volume 149

Number 1 | Number 2 | Number 3

Number 1

Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities

Marko Maucec, Bogdan Glumac

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 1-13

Technical Paper / Reactor Safety

A New Apparatus for Determination of the Free Volume of a Fuel Rod Using the Double Expansion Method

Lionel Desgranges, Marie-Hèlene Faure, Alain Thouroude

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 14-21

Technical Paper / Fuel Cycle and Management

The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design

Ser Gi Hong, Ehud Greenspan, Yeong Il Kim

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 22-48

Technical Paper / Fuel Cycle and Management

Computational Fluid Dynamics Prediction of Grid Spacer Thermal-Hydraulic Performance with Comparison to Experimental Results

Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 49-61

Technical Paper / Thermal Hydraulics

Numerical Optimization for the Design of a Spacer Grid with Mixing Vanes in a Pressurized Water Reactor Fuel Assembly

Kwang-Yong Kim, Jun-Woo Seo

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 62-70

Technical Paper / Thermal Hydraulics

Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code

Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, Young-Min Kwon, Yong-Bum Lee

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 71-87

Technical Paper / Thermal Hydraulics

Experimental Research on In-Tube Condensation Under Steady-State and Transient Conditions

Ali Tanrikut, Orhan Yesin

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 88-100

Technical Paper / Thermal Hydraulics

Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach

Iraci Martinez Gonçalves, Daniel K. S. Ting, Paulo Brasko Ferreira, Belle R. Upadhyaya

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 101-109

Technical Paper / Nuclear Plant Operations and Control

Performance-Based (Risk-Informed) Regulation: A Regulatory Perspective

N. Prasad Kadambi

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 110-121

Technical Paper / Miscellaneous

Review and Research of the Neutron Source Multiplication Method in Nuclear Critical Safety

Yong-Qian Shi, Qing-Fu Zhu, He Tao

Nuclear Technology / Volume 149 / Number 1 / January 2005 / Pages 122-127

Technical Note / Reactor Safety

Number 2

The Impact of Uncertainties on the Performance of Passive Systems

Lorenzo P. Pagani, George E. Apostolakis, Pavel Hejzlar

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 129-140

Technical Paper / Reactor Safety

Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel

Mikio Sakai, Toshihiro Yamamoto, Minoru Murazaki, Yoshinori Miyoshi

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 141-149

Technical Paper / Reactor Safety

Dynamics of Critical Dedicated Cores for Minor Actinide Transmutation

S. Massara, J. Tommasi, M. Vanier, O. Köberl

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 150-174

Technical Paper / Fuel Cycle and Management

Impact of Pin-by-Pin Thermal-Hydraulic Feedback Modeling on Steady-State Core Characteristics

Akio Yamamoto, Tsutomu Ikeno

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 175-188

Technical Paper / Thermal Hydraulics

Thermal Interaction Between Molten Metal Jet and Sodium Pool: Effect of Principal Factors Governing Fragmentation of the Jet

Satoshi Nishimura, Izumi Kinoshita, Ken-Ichiro Sugiyama, Nobuyuki Ueda

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 189-199

Technical Paper / Thermal Hydraulics

Integral Test and Engineering Analysis of Coolant Depletion During a Large-Break Loss-of-Coolant Accident

Yong Soo Kim, Chang Hwan Park, Byoung Uhn Bae, Goon Cherl Park, Kune Yull Suh, Un Chul Lee

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 200-216

Technical Paper / Thermal Hydraulics

Development of a New Aqueous Process for Nuclear Fuel Reprocessing: Hot Tests on the Recovery of U and Pu from a Nitric Acid Solution of Spent LWR Fuel

Yuezhou Wei, Tsuyoshi Arai, Harutaka Hoshi, Mikio Kumagai, Aimé Bruggeman, Patrick Goethals

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 217-231

Technical Paper / Reprocessing

Chlorine Release from Hypalon Cable Insulation During Severe Nuclear Reactor Accidents

Ari Auvinen, Riitta Zilliacus, Jorma Jokiniemi

Nuclear Technology / Volume 149 / Number 2 / February 2005 / Pages 232-241

Technical Paper / Radioisotopes

Number 3

Assessment on Integrity of BWR Internals Against Impact Load by Water Hammer Under Conditions of Reactivity Initiated Accidents

Mie Azuma, Atsushi Taniguchi, Akitoshi Hotta, Takeshi Ohta

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 243-252

Technical Paper / Fission Reactors

Assessments of Water Ingress Accidents in a Modular High-Temperature Gas-Cooled Reactor

Zuoyi Zhang, Yujie Dong, Winfried Scherer

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 253-264

Technical Paper / Fission Reactors

Peach Bottom Turbine Trip Simulations with RETRAN Using INER/TPC BWR Transient Analysis Method

Lainsu Kao, Show-Chyuan Chiang

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 265-280

Technical Paper / Reactor Safety

A Combined Nonfertile and UO2 PWR Fuel Assembly for Actinide Waste Minimization

Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 281-303

Technical Paper / Fuel Cycle and Management

VVER-1000 Model Assessment Using RELAP5-3D

Emilian L. Popov, Graydon L. Yoder, Valeri Velichkov

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 304-308

Technical Paper / Thermal Hydraulics

The Effect of the UO2/ZrO2 Composition on Fuel/Coolant Interaction

Jin Ho Song, Jong Hwan Kim

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 309-323

Technical Paper / Thermal Hydraulics

Brayton Cycle for High-Temperature Gas-Cooled Reactors

Chang H. Oh, Richard L. Moore

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 324-336

Technical Paper / Thermal Hydraulics

Screening Experiments for Removal of Low-Level Tritiated Water

Yun Mi Kim, Ronald Baney, Kevin Powers, Ben Koopman, James Tulenko

Nuclear Technology / Volume 149 / Number 3 / March 2005 / Pages 337-342

Technical Note / Nuclear Plant Operations and Control

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