Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13

Total loss of flow benchmark in CIRCE-HERO integral test facility

(2021) P. Lorusso et al.   NUCLEAR ENGINEERING AND DESIGN

Analysis of thermal stratification phenomena in the CIRCE-HERO facility

(2020) F. Buzzi et al.   ANNALS OF NUCLEAR ENERGY

Preliminary evaluation of ALFRED revised concept under station blackout

(2020) Vincenzo Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors

(2020) Zeyun Wu et al.   PROGRESS IN NUCLEAR ENERGY

STH/CFD Coupled Simulation of the Protected Loss of Flow Accident in the CIRCE-HERO Facility

(2020) Pucciarelli Andrea et al.   Applied Sciences-Basel

ALFRED reactor coolant system design

(2020) Alessandro Alemberti et al.   NUCLEAR ENGINEERING AND DESIGN

Experimental analysis of stationary and transient scenarios of alfred steam generator bayonet tube in circe-hero facility

(2019) P. Lorusso et al.   NUCLEAR ENGINEERING AND DESIGN

Investigation on RELAP5-3D© capability to predict thermal stratification in liquid metal pool-type system and comparison with experimental data

(2019) Vincenzo Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

CFD modelling of the CIRCE facility

(2019) K. Zwijsen et al.   NUCLEAR ENGINEERING AND DESIGN

Post-test simulations for the NACIE-UP benchmark by STH codes

(2019) N. Forgione et al.   NUCLEAR ENGINEERING AND DESIGN

System thermal-hydraulic modelling of the phénix dissymmetric test benchmark

(2019) V. Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

Post-test simulation of a PLOFA transient test in the CIRCE-HERO facility

(2019) V. Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

Pre-test analysis of accidental transients for ALFRED SGBT mock-up characterization

(2018) Vincenzo Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient

(2016) D. Castelliti et al.   NUCLEAR TECHNOLOGY

Validation of a Three-Dimensional Model of EBR-II and Assessment of RELAP5-3D Based on SHRT-17 Test

(2016) Alessandro Del Novo et al.   NUCLEAR TECHNOLOGY

RELAP5 and SIMMER-III code assessment on CIRCE decay heat removal experiments

(2015) Giacomino Bandini et al.   NUCLEAR ENGINEERING AND DESIGN

Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors

(2015) G. Bandini et al.   NUCLEAR ENGINEERING AND DESIGN

Mixed convection and stratification phenomena in a heavy liquid metal pool

(2015) Mariano Tarantino et al.   NUCLEAR ENGINEERING AND DESIGN

Numerical study on thermal stratification phenomena in upper plenum of LMFBR “MONJU”

(2013) Makoto Shibahara et al.   NUCLEAR ENGINEERING AND DESIGN

Sensitivity analysis of the MASLWR helical coil steam generator using TRACE

(2010) F. Mascari et al.   NUCLEAR ENGINEERING AND DESIGN

On the use of RELAP5-3D as a subchannel analysis code

(2009) Matthew Memmott et al.   NUCLEAR ENGINEERING AND DESIGN