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Volume 210

Number 2

Table of Contents
Foreword: Special issue on the Power-to-Melt and Maneuverability (P2M) Simulation Exercise(Jerome Sercombe)

P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments

V. D’Ambrosi, J. Sercombe, S. Bejaoui, A. Chaieb, B. Baurens, R. Largenton, A. Ambard, B. Boer, G. Bonny, M. Ševeček, L. E. Herranz, F. Feria Marquez, K. Inagaki, H. Ohta, F. Boldt, J. Sappl, R. Armstrong, A. Mohamad, Y. Udagawa, C. Cozzo, J. Klouzal, M. Vitezslav, J. Corson, J. Peltonen

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 189-215

Research Article / dx.doi.org/10.1080/00295450.2023.2194270

The UO₂ Power-to-Melt Experiment Performed in the High Burnup Chemistry International Program

G. Bonny, P. Blanpain, D. Rozzia, S. Billiet, M. Verwerft, B. Boer

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 216-231

Research Article / dx.doi.org/10.1080/00295450.2023.2264505

Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code CYRANO3

A. Chaieb, R. Largenton, A. Ambard, B. Baurens, M. Ton That

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 232-244

Research Article / dx.doi.org/10.1080/00295450.2023.2232664

Modeling of the P2M Past Fuel Melting Experiments with the FEMAXI-8 Code

Afiqa Mohamad, Yutaka Udagawa

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 245-260

Research Article / dx.doi.org/10.1080/00295450.2023.2185061

Modeling of the P2M Past Fuel Melting Experiments with the Fuel Performance Code FAST-1.0.1

James Corson, Alice Chung, Steven Muller

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 261-268

Research Article / dx.doi.org/10.1080/00295450.2023.2181042

2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment with the Fuel Performance Code ALCYONE

J. Sercombe, V. D’Ambrosi, S. Béjaoui, I. Zacharie-Aubrun

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 269-284

Research Article / dx.doi.org/10.1080/00295450.2023.2188138

Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE

V. D’Ambrosi, J. Sercombe, S. Béjaoui, I. Zacharie-Aubrun, C. Introïni, J. Karlsson, D. Jädernäs, H.-U. Zwicky

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 285-307

Research Article / dx.doi.org/10.1080/00295450.2023.2253660

Fuel Melting Simulation with FRAPCON/FRAPTRAN Codes for the Power-to-Melt-and-Maneuverability Simulation Exercise and Consideration of Model Modifications

Kenta Inagaki

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 308-323

Research Article / dx.doi.org/10.1080/00295450.2023.2239041

Modeling of OECD/NEA P2M Benchmark Cases by Means of TRANSURANUS Code

D. Rozzia, G. Bonny, S. Billiet, B. Boer, M. Verwerft

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 324-353

Research Article / dx.doi.org/10.1080/00295450.2023.2229186

Determination of the Gas Plenum Temperature of the P2M Instrumented Fuel Rodlets on the Basis of a Thermal-Hydraulic Study of the Belgian Reactor 2 Pressurized Water Capsule

A. Fayet, S. Béjaoui, T. Cadiou, J. Perez-Manes, E. Deveaux, A. Vernier, V. D’Ambrosi, J. Sercombe, C. Nonon-Solaro, G. Bignan, C. Koren, S. Mimouni, A. Ambard, B. Rossaert, P. Gouat, B. Boer, R. Wouter-Bosch

Nuclear Technology / Volume 210 / Number 2 / February 2024 / Pages 354-377

Research Article / dx.doi.org/10.1080/00295450.2023.2271222