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Volume 177

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Number 1

Homogenization of Cross Sections and Computation of Discontinuity Factors for a Real 3-D BWR Bottom Reflector for Comparison with Lattice and Nodal Codes

John Loberg, Michael ÖSterlund, Klaes-Håkan Bejmer, Jan Blomgren, Jesper Kierkegaard

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 1-7

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13323

Boiling Water Reactor Stability Analysis by TRACE/PARCS: Modeling Effects and Case Study of Time Versus Frequency Domain Approach

Rui Hu, Mujid S. Kazimi

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 8-28

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13324

Evaluation of Plutonium Hemisphere Critical Experiments Partially Reflected by Steel and Oil

John D. Bess

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 29-35

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-A13325

Modeling and Interpretation of Iodine Behavior in PHEBUS FPT-1 Containment with ASTEC and COCOSYS Codes

L. Bosland, G. Weber, W. Klein-Hessling, N. Girault, B. Clement

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 36-62

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT12-A13326

Development of Erbia-Credit Super High Burnup Fuel: Experiments and Numerical Analyses

Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 63-72

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A13327

Analysis of MERCI Decay Heat Measurement for PWR UO2 Fuel Rod

J. C. Jaboulay, S. Bourganel

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 73-82

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A13328

Minor Actinide Transmutation in GFR600

Zoltán Perkó, Jan Leen Kloosterman, Sándor Fehér

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 83-97

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A13329

Numerical Study on the Turbulent Mixing Coefficient for Supercritical Fluids in Subchannels

Yina Zhang, Chao Zhang, Jin Jiang

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 98-106

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13330

Experimental Study of Two-Phase Flow Regime and Pressure Drop in a Particulate Bed Packed with Multidiameter Particles

Liangxing Li, Shengjie Gong, Weimin Ma

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 107-118

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13331

PARET-ANL Modeling of a SPERT-IV Experiment Under Different Departure from Nucleate Boiling Correlations

S. Chatzidakis, A. Ikonomopoulos, S. E. Day

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 119-131

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13332

Probabilistic Kernel Approach to Online Monitoring of Nuclear Power Plants

Miltiadis Alamaniotis, Andreas Ikonomopoulos, Lefteri H. Tsoukalas

Nuclear Technology / Volume 177 / Number 1 / January 2012 / Pages 132-145

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A13333

Number 2

New Strategy on the Evaluation of Dancoff Factor in a Pebble Bed Reactor Using Monte Carlo Method

Song Hyun Kim, Hong-Chul Kim, Jong Kyung Kim, Jea Man Noh

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 147-156

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13362

Combined Micro and Macro Parameter Perturbation Theory and Application for BWR Lattice Design and Optimization

Albert G. Gu

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 157-175

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13363

Three-Field Countercurrent Flow Limitation Model

Jeffrey W. Lane, David L. Aumiller, Jr., Lawrence E. Hochreiter, Fan-Bill Cheung

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 176-187

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13364

Experiments on Steam Condensation and Temperature Distribution Within the IRWST of APR-1400

S. N. Kim

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 188-202

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13365

A Study on the Steady-State and Transient Behavior of Natural Circulation in REX-10

Byeong-Il Jang, Moo Hwan Kim, Gyoodong Jeun

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 203-216

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13366

Experimental Study of the Effect of Graphite Dispersion on the Heat Transfer Phenomena in a Reactor Cavity Cooling System

Rodolfo Vaghetto, Luigi Capone, Yassin A. Hassan

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 217-230

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13367

Verification of a Simple Procedure to Simulate Solvent Extraction by Pulsed Columns

Tsuguyuki Kobayashi

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 231-244

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT12-A13368

Effects of Variable Saturation on the Thermal Analysis of the Engineered Barrier System for a Nuclear Waste Repository

Won-Jin Cho, Sangki Kwon

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 245-256

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT12-A13369

Thermal Creep Model for CWSR Zircaloy-4 Cladding Taking into Account the Annealing of the Irradiation Hardening

Chantal Cappelaere, Roger Limon, Christelle Duguay, Gérard Pinte, Michel Le Breton, Pol Bouffioux, Valérie Chabretou, Alain Miquet

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 257-272

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT12-A13370

Wavelet Approach for Operational Gamma Spectral Peak Detection: Preliminary Assessment

D. Yuan, P. Guss, T. Ashenfelter

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 273-284

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT12-A13371

Feasibility Studies for Speckle Interferometry Used to Measure Deformation in Nuclear Fuel Cladding

Alexandre Vauselle, Yves Pontillon, Laurent Gallais

Nuclear Technology / Volume 177 / Number 2 / February 2012 / Pages 285-292

Technical Paper / Radiation Measurements and General Instrumentation / dx.doi.org/10.13182/NT12-A13372

Number 3

Comparison of Sodium-Cooled Reactor Fuel-Handling Systems With and Without an Ex-Vessel Storage Tank

Yoshitaka Chikazawa, Masayuki Uzawa, Shinichi Usui, Katsuhiro Tozawa, Shoji Kotake

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 293-302

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13476

ELECTRA: European Lead-Cooled Training Reactor

Janne Wallenius, Erdenechimeg Suvdantsetseg, Andrei Fokau

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 303-313

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT12-A13477

Mathematical Modeling and Its Applications for Mass Flow in a Nuclear Fuel Cycle

Raphael Craplet, Joonhong Ahn

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 314-335

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT12-A13478

Experimental Study of Thermal Mixing in Flow Mixing Header Assembly of SMART

Jong-Won Kim, Jong-Soo Choi, Young-In Kim, Young-Jong Chung, Goon-Cherl Park

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 336-351

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13479

A Practical Method for Whole-Core Thermal Analysis of a Prismatic Gas-Cooled Reactor

Nam-Il Tak, Min-Hwan Kim, Hong Sik Lim, Jae Man Noh

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 352-365

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-A13480

A Functionally Graded Composite for Service in High-Temperature Lead- and Lead-Bismuth-Cooled Nuclear Reactors - I: Design

Michael Philip Short, Ronald George Ballinger

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 366-381

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A13481

Integral Effect Tests on Transient Thermal-Hydraulic Behavior During a Steam Generator Tube Rupture Accident in the APR1400

Kyoung-Ho Kang, Hyun-Sik Park, Seok Cho, Nam-Hyun Choi, In-Cheol Chu, Byong-Jo Yun, Kyung-Doo Kim, Yeon-Sik Kim, Won-Pil Baek, Ki-Yong Choi

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 382-394

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT12-A13482

Nuclear Transmutations in HFIR's Beryllium Reflector and Their Impact on Reactor Operation and Reflector Disposal

David Chandler, G. Ivan Maldonado, L. D. Proctor, R. T. Primm, III

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 395-412

Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT12-A13483

Measurement and Modeling of Light Yield Nonproportionality in Neutron Detectors

Martin R. Williamson, Laurence F. Miller, Indraneel Sen

Nuclear Technology / Volume 177 / Number 3 / March 2012 / Pages 413-420

Technical Paper / Radiation Measurements and General Information / dx.doi.org/10.13182/NT12-A13484

 
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