ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT05-A3575

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 / dx.doi.org/10.13182/NT05-A3576

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 / dx.doi.org/10.13182/NT05-A3577

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 / dx.doi.org/10.13182/NT05-A3578

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 / dx.doi.org/10.13182/NT05-A3579

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 / dx.doi.org/10.13182/NT05-A3580

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 / dx.doi.org/10.13182/NT05-A3581

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 / dx.doi.org/10.13182/NT05-A3582

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 / dx.doi.org/10.13182/NT05-A3583

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 / dx.doi.org/10.13182/NT05-2

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 / dx.doi.org/10.13182/NT149-129

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 / dx.doi.org/10.13182/NT05-A3586

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 / dx.doi.org/10.13182/NT05-A3587

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 / dx.doi.org/10.13182/NT05-A3588

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 / dx.doi.org/10.13182/NT05-A3589

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 / dx.doi.org/10.13182/NT05-A3590

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 / dx.doi.org/10.13182/NT05-A3591

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 / dx.doi.org/10.13182/NT05-A3592

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 / dx.doi.org/10.13182/NT05-A3593

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 / dx.doi.org/10.13182/NT05-A3594

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 / dx.doi.org/10.13182/NT05-A3595

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 / dx.doi.org/10.13182/NT05-A3596

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 / dx.doi.org/10.13182/NT05-A3597

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 / dx.doi.org/10.13182/NT05-A3598

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 / dx.doi.org/10.13182/NT05-A3599

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 / dx.doi.org/10.13182/NT05-A3600