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Home / Publications / Journals / Nuclear Technology / Volume 112 / Number 2

Volume 112

Number 2

Mitigation of an Anticipated Transient Without Scram Event in A Simplified Boiling Water Reactor by the Insertion of Fine-Motion Control Rods

Hasna J. Khan, Hsiang S. Cheng, Upendra S. Rohatgi

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 155-168

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35170

Independent Assessment of Melcor as A Severe Accident Thermal-Hydraulic/Source Term Analysis Tool

I. K. Madni

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 169-180

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35171

A Comparative Simulation of Feed and Bleed Operation During the Total Loss of Feedwater Event by RELAP5/MOD3 and CEFLASH-4AS/REM Computer Codes

Young Min Kwon, Tae Sun Ro, Jin Ho Song

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 181-193

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35172

Irradiation Performance of Fast Flux Test Facility Drivers Using D9 Alloy

A. L. Pitner, B. C. Gneiting, F. E. Bard

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 194-203

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35173

Choice of A Process Design for Simultaneous Detritiation and Upgrading of Heavy water for the Advanced Neutron Source

A. I. Miller, D. A. Spagnolo, J. R. DeVore

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 204-213

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT95-A35174

Taiwan Power Company’s Power Distribution Analysis and Fuel Thermal Margin Verification Methods for Pressurized Water Reactors

Ping-Hue Huang

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 214-226

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35175

Heat Transfer from A Plate Cooled by A Water Film with Countercurrent Air Flow

W. Ambrosini, A. Manfredini, F. Mariotti, F. Oriolo, P. Vigni

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 227-237

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35176

Thermal-Hydraulic Modeling and Severe Accident Radionuclide Transport

F. Oriolo, W. Ambrosini, G. Fruttuoso, F. Parozzi, R. Fontana

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 238-249

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35177

Probabilistic Analysis of Limiting Conditions for Operation Action Requirements Including Risk of Shutdown

T. Mankamo, I. S. Kim, P. K. Samanta

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 250-265

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35178

Development of the On-Line Operator Aid System OASYS Using A Rule-Based Expert System and Fuzzy Logic for Nuclear Power Plants

Soon Heung Chang, Ki Sig Kang, Seong Soo Choi, Han Gon Kim, Hee Kyo Jeong, Chul Un Yi

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 266-294

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35179

Transient Gap Conductance in Nuclear Fuel Rods

G. Dharmadurai

Nuclear Technology / Volume 112 / Number 2 / November 1995 / Pages 295-298

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35180

 

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