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Home / Publications / Journals / Nuclear Technology / Volume 153 / Number 1

Volume 153

Number 1

Application of the Pitzer Method for Modeling Densities of Actinide Solutions in the SCALE Code System

Charles F. Weber, Calvin M. Hopper

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 1-8

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3684

A Methodology for Developing a Probability Distribution for the Failure Enthalpy of High-Burnup Fuels via Simulation

Lorenzo P. Pagani, George E. Apostolakis

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 9-17

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3685

Fission Gas Release from Uranium-Zirconium Hydride Fuel During Heating to Melting

Yeon Soo Kim, Gerard L. Hofman, James L. Snelgrove

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 18-24

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3686

Progress of the DUPIC Fuel Compatibility Analysis - I: Reactor Physics

Hangbok Choi, Chang Joon Jeong, Gyu Hong Roh, Bo Wook Rhee, Myung Seung Yang

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 25-40

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3687

A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant

Young-Jong Chung, Hee-Kyung Kim, Hee-Cheol Kim, Sung-Quun Zee

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 41-52

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3688

A Generic Method to Evaluate the Reasonable Upper-Bound Dose from Near-Surface Radioactive Waste Disposal Facilities Through Drinking Water Pathway

R. N. Nair, Y. S. Mayya, V. D. Puranik

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 53-69

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3689

Extracting Risk Insights from Performance Assessments for High-Level Radioactive Waste Repositories

S.Tina Ghosh, George E. Apostolakis

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 70-88

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3690

The Applicability of a Quenching Mesh as a Hydrogen Flame Arrester in Nuclear Power Plants

Seong-Wan Hong, Jin-Ho Song, Hee-Dong Kim, Soon-Heung Chang

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 89-99

Technical Paper / Miscellaneous / dx.doi.org/10.13182/NT06-A3691

Development of Control Technology for the HTTR Hydrogen Production System

Tetsuo Nishihara, Yoshiyuki Inagaki

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 100-106

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3692

Alpha-Particle Low-Level Waste Control: Improvement of the PROMETHEE 6 Assay System Performances

Fanny Jallu, Alain Mariani, Christian Passard, Anne-Cecile Raoux, Herve Toubon

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 107-115

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3693

 

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