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Volume 127

Number 3

Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Safety Systems: Consequences of the Partial or Total Elimination of Soluble Boron on Plant Safety and Plant Systems Architecture

Gian Luigi Fiorini, Guy Marie Gautier, Yves Bergamaschi

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 239-258

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A2999

Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Core Physics - I: Motivations, Assembly Design, and Core Control

Paul Thomet

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 259-266

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT127-259

Feasibility Studies of a Soluble Boron-Free 900-MW(electric) PWR, Core Physics - II: Control Rod Follow, Load Follow, and Reactivity-Initiated Accident Linked to RCCAs

Jean-Paul Deffain, Philippe Alexandre, Paul Thomet

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 267-286

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT99-A3001

Hybrid Analysis of the Simplified Boiling Water Reactor Using RAMONA-4B and CASMO-3 Computer Codes

Gabriel F. Cuevas Vivas, Yassin A. Hassan

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 287-300

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3002

Benchmark Calculations of the ESADA Single-Region Mixed-Oxide Critical Experiments

Hatice Akkurt, Naeem M. Abdurrahman

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 301-314

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3003

Benchmark Calculations of the Saxton Plutonium Program Critical Experiments

Naeem M. Abdurrahman, Georgeta Radulescu, Igor Carron

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 315-331

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A3004

Behavior of a UF6 Container During a Fire - I: Analysis and Phenomenological Interpretation of Tenerife Experimental Results

Eric Pinton, Bernard Duret, Georges Berthoud

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 332-351

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3005

Behavior of a UF6 Container in a Fire - II: Modeling and Validation

Eric Pinton, Bernard Duret, Georges Berthoud

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 352-374

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3006

Uranium Dioxide Powder Preparation, Pressing, and Sintering for Optimum Yield

Palanki Balakrishna, Chandru K. Asnani, R. M. Kartha, K. Ramachandran, K. Sarat Babu, Vaidyanathan Ravichandran, Bhallamudi Narasimha Murty, Chaitanyamoy Ganguly

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 375-381

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A3007

Pressurized Water Reactor Coolant Pump Locked Rotor Analysis Methodology Using RETRAN-02 and FREY

Lainsu Kao, Ping-Hue Huang

Nuclear Technology / Volume 127 / Number 3 / September 1999 / Pages 382-388

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A3008

 

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