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Volume 142

Number 2

Using the OECD/NRC Pressurized Water Reactor Main Steam Line Break Benchmark to Study Current Numerical and Computational Issues of Coupled Calculations

Kostadin N. Ivanov, Nadejda K. Todorova, Enrico Sartori

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 95-115

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3376

Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE

Antti Daavittila, Anitta Hämäläinen, Riitta Kyrki-Rajamäki

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 116-123

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3377

Analysis of the Pressurized Water Reactor Main Steam Line Break Benchmark by the Coupled Code System ATHLET-QUABOX/CUBBOX

Siegfried Langenbuch, Klaus-Dieter Schmidt, Kiril Velkov

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 124-136

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3378

Sensitivity Studies for Main Steam Line Break Exercises 2 and 3 with RELAP5/PANBOX

Rainer Böer, Alfred Knoll

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 137-145

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3379

Analyses of the OECD Main Steam Line Break Benchmark with the DYN3D and ATHLET Codes

Ulrich Grundmann, Sören Kliem

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 146-153

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3380

CEA-IRSN Participation in the Main Steam Line Break Benchmark

E. Royer, E. Raimond, D. Caruge

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 154-165

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3381

Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code

Han Gyu Joo, Jae-Jun Jeong, Byung-Oh Cho, Won Jae Lee, Sung Quun Zee

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 166-179

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT142-166

Three Mile Island Unit 1 Main Steam Line Break Three-Dimensional Neutronics/Thermal-Hydraulics Analysis: Application of Different Coupled Codes

Francesco D'Auria, José Luis Gago Moreno, Giorgio Maria Galassi, Davor Grgic, Antonino Spadoni

Nuclear Technology / Volume 142 / Number 2 / May 2003 / Pages 180-204

Technical Paper / OECD/NRC MSLB Benchmark / dx.doi.org/10.13182/NT03-A3383

 

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