This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOCA) and the loss-of-feedwater accident (LOFW) in a scaled integral test facility of REX-10. REX-10 is a small integral-type PWR in which the coolant flow is driven by natural circulation, and the RCS is pressurized by the steam-gas pressurizer. The postulated accidents of REX-10 include the system depressurization initiated by the break of a nitrogen injection line connected to the steam-gas pressurizer and the complete loss of normal feedwater flow by the malfunction of control systems. The integral effect tests on SBLOCA and LOFW are conducted at the REX-10 Test Facility (RTF), a full-height full-pressure facility with reduced power by 1/50....
A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (L...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...
This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermedia...
This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOC...
A small-scale nonnuclear integral test facility designed to simulate a pressurized water reactor (PW...
An experiment was performed for the OECD/NEA ROSA-2 Project employing the ROSA/LSTF (rig of safety a...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
An experiment on a PWR station blackout transient with the TMLB' scenario and accident manageme...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyse...
A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (L...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...
This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermedia...
This paper presents an experimental investigation of the small-break loss-of-coolant accident (SBLOC...
A small-scale nonnuclear integral test facility designed to simulate a pressurized water reactor (PW...
An experiment was performed for the OECD/NEA ROSA-2 Project employing the ROSA/LSTF (rig of safety a...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechani...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
Thermal-hydraulic analysis is a key part in support of regulatory work and nuclear power plant desig...
An experiment on a PWR station blackout transient with the TMLB' scenario and accident manageme...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
International audienceThermal-hydraulic analysis is a key part in support of regulatory work and nuc...
Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyse...
A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (L...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...
This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermedia...