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Home / Publications / Journals / Nuclear Science and Engineering / Volume 148 / Number 2

Volume 148

Number 2

OECD/NRC BWR Turbine Trip Transient Benchmark as a Basis for Comprehensive Qualification and Studying Best-Estimate Coupled Codes

Kostadin Ivanov, Andy Olson, Enrico Sartori

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 195-207

Technical Paper / dx.doi.org/10.13182/NSE04-A2451

Application of TRAC/BF1-ENTRÉE-NASCA to OECD NEA/NSC BWR Turbine Trip Benchmark

Akitoshi Hotta, Minyan Zhang, Hiroshi Shirai

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 208-225

Technical Paper / dx.doi.org/10.13182/NSE04-A2452

Analysis of the Boiling Water Reactor Turbine Trip Benchmark with the Codes DYN3D and ATHLET/DYN3D

Ulrich Grundmann, Sören Kliem, Ulrich Rohde

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 226-234

Technical Paper / dx.doi.org/10.13182/NSE04-A2453

Computation of a BWR Turbine Trip with CATHARE-CRONOS2-FLICA4 Coupled Codes

G. Mignot, E. Royer, B. Rameau, N. Todorova

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 235-246

Technical Paper / dx.doi.org/10.13182/NSE04-A2454

OECD/NRC BWR Turbine Trip Benchmark: Simulation by POLCA-T Code

Dobromir Panayotov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 247-255

Technical Paper / dx.doi.org/10.13182/NSE04-A2455

Peach Bottom Transients Analysis with TRAC/BF1-VALKIN

G. Verdú, R. Miró, A. M. Sánchez, O. Roselló, D. Ginestar, V. Vidal

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 256-269

Technical Paper / dx.doi.org/10.13182/NSE04-A2456

Analysis of the OECD/NRC BWR Turbine Trip Benchmark by the Coupled-Code System ATHLET-QUABOX/CUBBOX

S. Langenbuch, K.-D. Schmidt, K. Velkov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 270-280

Technical Paper / dx.doi.org/10.13182/NSE04-A2457

Peach Bottom 2 Turbine Trip Simulation Using TRAC-BF1/COS3D, a Best-Estimate Coupled 3-D Core and Thermal-Hydraulic Code System

Atsushi Ui, Takamasa Miyaji

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 281-290

Technical Paper / dx.doi.org/10.13182/NSE04-A2458

Analysis of the OECD/NRC BWR Turbine Trip Transient Benchmark with the Coupled Thermal-Hydraulics and Neutronics Code TRAC-M/PARCS

Deokjung Lee, Thomas J. Downar, Anthony Ulses, Bedirhan Akdeniz, Kostadin N. Ivanov

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 291-305

Technical Paper / dx.doi.org/10.13182/NSE04-A2459

Peach Bottom BWR Turbine Trip Benchmark Analyses with RETRAN-3D and CORETRAN

W. Barten, H. Ferroukhi, P. Coddington

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 306-324

Technical Paper / dx.doi.org/10.13182/NSE04-A2460

SIMULATE-3K Peach Bottom 2 Turbine Trip 2 Benchmark Calculations

Lotfi A. Belblidia, Gerardo M. Grandi, Christian Jönsson

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 325-336

Technical Paper / dx.doi.org/10.13182/NSE04-A2461

Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes

Anis Bousbia-Salah, Juswald Vedovi, Francesco D'Auria, Kostadin Ivanov, Giorgio Galassi

Nuclear Science and Engineering / Volume 148 / Number 2 / October 2004 / Pages 337-353

Technical Paper / dx.doi.org/10.13182/NSE04-A2462

 

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