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Home / Publications / Journals / Nuclear Technology / Volume 156

Volume 156

Number 1 | Number 2 | Number 3

Number 1

Evaluation of Working Fluids in an Indirect Combined Cycle in a Very High Temperature Gas-Cooled Reactor

Chang H. Oh, Robert Barner, Cliff Davis, Steven Sherman

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 1-10

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3769

Radiochemistry of Iodine: Outcomes of the CAIMAN Program

L. Cantrel

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 11-28

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT156-11

Direct Simulation Monte Carlo Aerosol Dynamics: Coagulation and Collisional Sampling

Geethpriya Palaniswaamy, Sudarshan K. Loyalka

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 29-38

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3771

Development and Verifications of Fast Reactor Fuel Design Code CEPTAR

T. Ozawa, T. Abe

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 39-55

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT156-39

Investigation of the Downcomer Boiling Phenomena During the Reflood Phase of a Postulated Large-Break LOCA in the APR1400

Byong-Jo Yun, Dong-Jin Euh, Chul-Hwa Song

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 56-68

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3773

Validation of COBRA-TF Critical Heat Flux Predictions for a Small-Hydraulic-Diameter Geometry Under Natural Boiling Conditions

Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 69-74

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3774

Treatment of Nuclear Data for Transport Problems Containing Detailed Temperature Distributions

T. H. Trumbull

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 75-86

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT156-75

Caustic Precipitation of Plutonium and Uranium with Gadolinium as a Neutron Poison

Ann E. Visser, Michael G. Bronikowski, Tracy S. Rudisill

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 87-98

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT06-A3776

A Subcritical, Helium-Cooled Fast Reactor for the Transmutation of Spent Nuclear Fuel

W. M. Stacey, Z. Abbasi, C. J. Boyd, A. H. Bridges, E. A. Burgett, M. W. Cymbor, S. W. Fowler, A. T. Jones, R. S. Kelm, B. J. Kern, D. B. Lassiter, J. A. Maddox, W. B. Murphy, H. Park, J. M. Pounders, J. R. Preston

Nuclear Technology / Volume 156 / Number 1 / October 2006 / Pages 99-123

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3777

Number 2

Developing a Tool for Simulating the Behavior of Axial Flux Difference During Power Reduction for Maanshan Pressurized Water Reactor Units

Jau-Tyne Yeh, Ta-Lun Sung, J. Y. Shiue

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 125-132

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3778

Simulation of a PWR Reactor Vessel Level Indicating System During Station Blackout with MELCOR 1.8.5

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 133-139

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3779

Off-Gas Source Estimation for Boiling Water Reactors Under Various Operation Conditions

Masato Takahashi

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 140-149

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3780

Failure Mode and Effect Analysis Application for the Safety and Reliability Analysis of a Thermal-Hydraulic Passive System

Luciano Burgazzi

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 150-158

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3781

Enhancement of Safety Analysis Capability for a CANDU-6 Reactor Using RELAP-CANDU/SCAN Coupled Code System

Manwoong Kim, Hyun-Koon Kim, Hho-Jung Kim, Su Hyon Hwang, In Seob Hong, Chang Hyo Kim

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 159-167

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3782

Genetic Algorithm to Optimize the UO2/Gd2O3 Fuel Pin Designs in a Pressurized Water Reactor

Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 168-179

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3783

Genetic Algorithm Application for Burnable Poison Placement in PWRs with Optimized UO2/Gd2O3 Fuel Pin Configurations

Serkan Yilmaz, Kostadin Ivanov, Samuel Levine, Moussa Mahgerefteh

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 180-190

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3784

Assessment of S/R5/MOD3.3 Models of Stratified Molten Pool and Debris-to-Vessel Contact Resistance by TMI-2 Lower-Head Creep Rupture Analyses

Sang Lung Chan

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 191-212

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3785

Properties of Titanium-Nitride for High-Level Waste Packaging Enhancement

C. C. Scheffing, K. Jagannadham, M.-S. Yim, M. A. Bourham, J. C. Farmer, J. J. Haslam, S. D. Day, D. V. Fix, N. Y. Yang

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 213-221

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT156-213

Numerical Study of Nuclide Migration in a Nonuniform Horizontal Flow Field of a High-Level Radioactive Waste Repository with Multiple Canisters

Doo-Hyun Lim

Nuclear Technology / Volume 156 / Number 2 / November 2006 / Pages 222-245

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3787

Number 3

Assessment of a MOX Fuel Assembly Design for a BWR Mixed Reload

J. Ramon Ramirez, Gustavo Alonso, Robert T. Perry, Javier Ortiz-Villafuerte

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 247-255

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3788

Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents

Ki Yong Choi, Hyun Sik Park, Dong Jin Euh, Tae Soon Kwon, Won Pil Baek

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 256-269

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3789

Detailed Analysis of Late-Phase Core-Melt Progression for the Evaluation of In-Vessel Corium Retention

R. J. Park, S. B. Kim, K. Y. Suh, J. L. Rempe, F. B. Cheung

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 270-281

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3790

Microgravity Phase Separation for the Rankine Cycle

Melissa Ghrist, Mike Ellis, David Bean, Cable Kurwitz, Frederick Best

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 282-288

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3791

A New Approach to Treating the Cell Property Averaging for a System Heat Transfer Analysis

Yoon Sub Sim

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 289-302

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3792

Linear Programming Approach for Optimization of Radionuclide Loading in Vitrified HLW

Joonhong Ahn, Myeongguk Cheon

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 303-319

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3793

Thermocouples for High-Temperature In-Pile Testing

J. L. Rempe, D. L. Knudson, K. G. Condie, S. Curtis Wilkins

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 320-331

Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT06-A3794

Review of Literature on Ruthenium Behavior in Nuclear Power Plant Severe Accidents

C. Mun, L. Cantrel, C. Madic

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 332-346

Technical Note / Reactor Safety / dx.doi.org/10.13182/NT156-332

Effectiveness of the Raw-Water System as a Severe-Accident-Management Measure in Station Blackout Accidents

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 347-359

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3796

Improvement of the Subchannel Flow Mixing Model of the MARS Code

Jae Jun Jeong, Dae Hyun Hwang, Bub Dong Chung

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 360-368

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3797

 

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