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...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...
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...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...
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...
As research regarding small- and medium-sized nuclear reactors (SMRs) has rapidly increased worldwid...