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Volume 148

Number 1

Development of NSSS Thermal-Hydraulic Model for KNPEC-2 Simulator Using the Best-Estimate Code RETRAN-3D

Kyung-Doo Kim, Jae-Jun Jeong, Seung-Wook Lee, Myeong-Soo Lee, Jae-Seung Suh, Jin-Hyuk Hong, Yong-Kwan Lee

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 3-11

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3543

Modeling and Simulation of the ABWR with Transient Analyses for Validation of RETRAN-3D/MOD003

Michitsugu Mori

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 12-24

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3544

Benchmarking NSP Reactors with CORETRAN-01

Donald D. Hines, Rodney L. Grow, Lance J. Agee

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 25-34

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3545

Pretest Calculations of Phase A of ISP-42 (PANDA) Using the GOTHIC Containment Code and Comparison with the Experimental Results

Michele Andreani

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 35-47

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3546

Oconee Nuclear Power Station Main Steam Line Break Analysis for Steam Generator Tube Stress Evaluation

Jan S. Muransky, John G. Shatford, Craig E. Peterson, Gregg B. Swindlehurst

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 48-55

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3547

Development of Non-LOCA Safety Analysis Methodology with RETRAN-3D and VIPRE-01/K

Yo-Han Kim, Ae-Ju Cheong, Chang-Keun Yang

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 56-67

Technical Paper / RETRAN / dx.doi.org/10.13182/NT04-A3548

TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel

Jing Wang, Ronald G. Ballinger, Heather J. Maclean

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 68-96

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT04-A3549

Some Considerations on 242mAm Production in Thermal Reactors

Alessandra Cesana, Sara Tania Mongelli, Mario Terrani, Pietro Benetti, Elio Calligarich, Rinaldo Dolfini, Gian Luca Raselli

Nuclear Technology / Volume 148 / Number 1 / October 2004 / Pages 97-101

Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT04-A3550