Conference Agenda
• Please select a date or location to show only sessions at that day or location. • Please select a single session for detailed view such as the presentation order, authors’ information and abstract etc. • Please click ‘Session Overview’ to return to the overview page after checking each session.
|
Session Overview |
| Session | ||
Keynote 1
| ||
| Presentations | ||
ID: 3089
/ Keynote 1: 1
Invited Paper Keywords: Passive system, thermal hydraulics, ROSA-AP600, PCCS, computer codes Personal Experiences in the Two Kinds of Experiments to Confirm Reliability of Passive Systems for Nuclear Reactors Japan Atomic Energy Agency, Japan Passive systems (PSs), both for reactor driving system and safety features, are currently significantly discussed because they will surely take an important role in the coming reactor designs including small modular reactors (SMRs), irrespective of water-cooled or non-water-cooled ones. Great many kinds of developmental effort are underway including the confirmation of their performances especially in the reactor safety aspects. While PSs should have many favorable points, their stability and thus reliability have been discussed with some concerns because of their small driving force especially in the coolant injection capability to maintain integrity of nuclear fuels under any kinds of accidents. This paper revisits two past efforts: ROSA-AP600 and passive containment cooling system (PCCS) horizontal heat exchanger for advanced boiling water reactor (ABWR) containment vessel under severe accident conditions, thus reactor system response and component performances of PSs, to consider key thermal-hydraulic capabilities assessed to assure the reliability in such a practical use of PSs. | ||
