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Volume 156

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