ANS / Publications / Journals / Nuclear Technology

Analysis and Preliminary Design of Primary Heat Exchanger Failure Testing Facility for Lead-Cooled Fast Reactors

Federico Hattab, Fabio Giannetti, Vincenzo Narcisi, Pierdomenico Lorusso, Filippo Bussoletti, Michael Epstein, Sung Jin Lee, Mariano Tarantino

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 543-564

Research Article / dx.doi.org/10.1080/00295450.2023.2173482

Steady-State and Transient Compliance of CIRCE-THETIS CFD Model

Manuela Profir, Vincent Moreau

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 565-578

Research Article / dx.doi.org/10.1080/00295450.2023.2175589

The Versatile Loop Facility: A New Infrastructure for Testing Components and Systems of Lead Fast Reactor Technology

M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, C. Stansbury, P. Ferroni

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 579-590

Research Article / dx.doi.org/10.1080/00295450.2023.2181043

Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop

Tommaso Del Moro, Fabio Giannetti, Mariano Tarantino, Pierdomenico Lorusso, Marco Caramello, Damiano Vitale Di Maio, Marin Constantin

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 591-607

Research Article / dx.doi.org/10.1080/00295450.2023.2183025

Experimental Analysis of Steam Generator Tube Rupture in CIRCE Facility for MYRRHA Configuration

Alessio Pesetti, Mariano Tarantino

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 608-628

Research Article / dx.doi.org/10.1080/00295450.2023.2185050

Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign

Pietro Stefanini, Francesco Galleni, Ivan Di Piazza, Andrea Pucciarelli

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 629-643

Research Article / dx.doi.org/10.1080/00295450.2023.2189892

Design and Assessment of the New CIRCE-THETIS Facility for the Development of Heavy Liquid Metal Cooled Fast Reactors

Pierdomenico Lorusso, Ivan Di Piazza, Daniele Martelli, Mariano Tarantino

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 644-665

Research Article / dx.doi.org/10.1080/00295450.2023.2189903

Westinghouse Test Facilities for Lead Fast Reactor Development

Sung Jin Lee, Michael Ickes, Jeffrey L. Arndt, Michael Epstein, Asfaq Patel, Paolo Ferroni

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 666-680

Research Article / dx.doi.org/10.1080/00295450.2023.2197667

Flow-Induced Vibration Experiment in Fuel Pin Bundle with Heavy Liquid Metal Flow: Test Section Design and Measurement Methods

I. Di Piazza, D. Martelli, C. Carrelli, T. Rovai, V. Raschioni, M. Ramacciotti, A. Spezzaneve, D. Ferretti, G. Mongiardini

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 681-691

Research Article / dx.doi.org/10.1080/00295450.2023.2203285

Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator

P. Cioli Puviani, I. Di Piazza, R. Marinari, R. Zanino, M. Tarantino

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 692-712

Research Article / dx.doi.org/10.1080/00295450.2023.2215682

Subchannel Analysis of LFR Wire-Wrapped Fuel Bundle with RELAP5-3D

Cristiano Ciurluini, Vincenzo Narcisi, Ivan Di Piazza, Fabio Giannetti

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 713-724

Research Article / dx.doi.org/10.1080/00295450.2023.2222248

Protected Loss-of-Flow Accident in a HLM Pool Facility: Long-Term Cooling Experiment

Mariano Tarantino, Pierdomenico Lorusso, Alessio Pesetti, Ivan Di Piazza, Daniele Martelli

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 725-739

Research Article / dx.doi.org/10.1080/00295450.2023.2226525

The Passive Heat Removal Facility: Testing and Demonstrating an Innovative Decay Heat Removal System

M. Caramello, M. Frignani, R. Beaumont, M. Tarantino, J. Liao, R. F. Wright, M. Durse, A. Wimshurst, P. Ferroni

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 740-757

Research Article / dx.doi.org/10.1080/00295450.2023.2241731

Preliminary Characterization of Alumina-Forming Austenitic–Type Advanced Alloys as Structural Materials for LFRs

A. Meli, S. Bassini, C. Ciantelli, A. Fiore, M. Angiolini, M. Tarantino

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 758-771

Research Article / dx.doi.org/10.1080/00295450.2023.2257547

Versatile Testing Facility for Heavy Liquid Metal–Cooled Fast Reactor at the University of Pittsburgh

Jung-Kun Lee, Sumin Bae, Sajib A. Dahr

Nuclear Technology / Volume 210 / Number 4 / April 2024 / Pages 772-780

Research Article / dx.doi.org/10.1080/00295450.2023.2277027