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Number 1 · January 2005
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Table of Contents
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Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities
Volume 149 · Number 1 · January 2005 · Pages 1-13
Technical Paper · Reactor Safety

Marko Maucec, Bogdan Glumac
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A New Apparatus for Determination of the Free Volume of a Fuel Rod Using the Double Expansion Method
Volume 149 · Number 1 · January 2005 · Pages 14-21
Technical Paper · Fuel Cycle and Management

Lionel Desgranges, Marie-Hèlene Faure, Alain Thouroude
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The Encapsulated Nuclear Heat Source (ENHS) Reactor Core Design
Volume 149 · Number 1 · January 2005 · Pages 22-48
Technical Paper · Fuel Cycle and Management

Ser Gi Hong, Ehud Greenspan, Yeong Il Kim
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Computational Fluid Dynamics Prediction of Grid Spacer Thermal-Hydraulic Performance with Comparison to Experimental Results
Volume 149 · Number 1 · January 2005 · Pages 49-61
Technical Paper · Thermal Hydraulics

Robert L. Campbell, John M. Cimbala, Lawrence E. Hochreiter
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Numerical Optimization for the Design of a Spacer Grid with Mixing Vanes in a Pressurized Water Reactor Fuel Assembly
Volume 149 · Number 1 · January 2005 · Pages 62-70
Technical Paper · Thermal Hydraulics

Kwang-Yong Kim, Jun-Woo Seo
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Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code
Volume 149 · Number 1 · January 2005 · Pages 71-87
Technical Paper · Thermal Hydraulics

Hae-Yong Jeong, Kwi-Seok Ha, Won-Pyo Chang, Young-Min Kwon, Yong-Bum Lee
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Experimental Research on In-Tube Condensation Under Steady-State and Transient Conditions
Volume 149 · Number 1 · January 2005 · Pages 88-100
Technical Paper · Thermal Hydraulics

Ali Tanrikut, Orhan Yesin
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Monitoring an Experimental Reactor Using the Group Method of Data Handling Approach
Volume 149 · Number 1 · January 2005 · Pages 101-109
Technical Paper · Nuclear Plant Operations and Control

Iraci Martinez Gonçalves, Daniel K. S. Ting, Paulo Brasko Ferreira, Belle R. Upadhyaya
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Performance-Based (Risk-Informed) Regulation: A Regulatory Perspective
Volume 149 · Number 1 · January 2005 · Pages 110-121
Technical Paper · Miscellaneous

N. Prasad Kadambi
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Review and Research of the Neutron Source Multiplication Method in Nuclear Critical Safety
Volume 149 · Number 1 · January 2005 · Pages 122-127
Technical Note · Reactor Safety

Yong-Qian Shi, Qing-Fu Zhu, He Tao
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Number 2 · February 2005
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Table of Contents
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The Impact of Uncertainties on the Performance of Passive Systems
Volume 149 · Number 2 · February 2005 · Pages 129-140
Technical Paper · Reactor Safety

Lorenzo P. Pagani, George E. Apostolakis, Pavel Hejzlar
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Development of a Criticality Evaluation Method Considering the Particulate Behavior of Nuclear Fuel
Volume 149 · Number 2 · February 2005 · Pages 141-149
Technical Paper · Reactor Safety

Mikio Sakai, Toshihiro Yamamoto, Minoru Murazaki, Yoshinori Miyoshi
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Dynamics of Critical Dedicated Cores for Minor Actinide Transmutation
Volume 149 · Number 2 · February 2005 · Pages 150-174
Technical Paper · Fuel Cycle and Management

S. Massara, J. Tommasi, M. Vanier, O. Köberl
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Impact of Pin-by-Pin Thermal-Hydraulic Feedback Modeling on Steady-State Core Characteristics
Volume 149 · Number 2 · February 2005 · Pages 175-188
Technical Paper · Thermal Hydraulics

Akio Yamamoto, Tsutomu Ikeno
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Thermal Interaction Between Molten Metal Jet and Sodium Pool: Effect of Principal Factors Governing Fragmentation of the Jet
Volume 149 · Number 2 · February 2005 · Pages 189-199
Technical Paper · Thermal Hydraulics

Satoshi Nishimura, Izumi Kinoshita, Ken-Ichiro Sugiyama, Nobuyuki Ueda
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Integral Test and Engineering Analysis of Coolant Depletion During a Large-Break Loss-of-Coolant Accident
Volume 149 · Number 2 · February 2005 · Pages 200-216
Technical Paper · Thermal Hydraulics

Yong Soo Kim, Chang Hwan Park, Byoung Uhn Bae, Goon Cherl Park, Kune Yull Suh, Un Chul Lee
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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
Volume 149 · Number 2 · February 2005 · Pages 217-231
Technical Paper · Reprocessing

Yuezhou Wei, Tsuyoshi Arai, Harutaka Hoshi, Mikio Kumagai, Aimé Bruggeman, Patrick Goethals
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Chlorine Release from Hypalon Cable Insulation During Severe Nuclear Reactor Accidents
Volume 149 · Number 2 · February 2005 · Pages 232-241
Technical Paper · Radioisotopes

Ari Auvinen, Riitta Zilliacus, Jorma Jokiniemi
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Number 3 · March 2005
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Table of Contents
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Assessment on Integrity of BWR Internals Against Impact Load by Water Hammer Under Conditions of Reactivity Initiated Accidents
Volume 149 · Number 3 · March 2005 · Pages 243-252
Technical Paper · Fission Reactors

Mie Azuma, Atsushi Taniguchi, Akitoshi Hotta, Takeshi Ohta
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Assessments of Water Ingress Accidents in a Modular High-Temperature Gas-Cooled Reactor
Volume 149 · Number 3 · March 2005 · Pages 253-264
Technical Paper · Fission Reactors

Zuoyi Zhang, Yujie Dong, Winfried Scherer
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Peach Bottom Turbine Trip Simulations with RETRAN Using INER/TPC BWR Transient Analysis Method
Volume 149 · Number 3 · March 2005 · Pages 265-280
Technical Paper · Reactor Safety

Lainsu Kao, Show-Chyuan Chiang
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A Combined Nonfertile and UO2 PWR Fuel Assembly for Actinide Waste Minimization
Volume 149 · Number 3 · March 2005 · Pages 281-303
Technical Paper · Fuel Cycle and Management

Eugene Shwageraus, Pavel Hejzlar, Mujid S. Kazimi
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VVER-1000 Model Assessment Using RELAP5-3D
Volume 149 · Number 3 · March 2005 · Pages 304-308
Technical Paper · Thermal Hydraulics

Emilian L. Popov, Graydon L. Yoder, Valeri Velichkov
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The Effect of the UO2/ZrO2 Composition on Fuel/Coolant Interaction
Volume 149 · Number 3 · March 2005 · Pages 309-323
Technical Paper · Thermal Hydraulics

Jin Ho Song, Jong Hwan Kim
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Brayton Cycle for High-Temperature Gas-Cooled Reactors
Volume 149 · Number 3 · March 2005 · Pages 324-336
Technical Paper · Thermal Hydraulics

Chang H. Oh, Richard L. Moore
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Screening Experiments for Removal of Low-Level Tritiated Water
Volume 149 · Number 3 · March 2005 · Pages 337-342
Technical Note · Nuclear Plant Operations and Control

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