Abstract
The 35 participants, representing 7 Member States and one International Organization discussed
recent investigations on leak development and propagation in LMFBR steam generators. The
meeting was divided into three technical sessions: review of national status on studies of failure
propagation (8 papers). Propagation experience on reactor steam generators (4 papers). Studies of
failure propagation: codes, hydrogen detection, tests (11 papers).
Content
- Introduction of the steam generator programs of the United States Department of Energy
- Status of U.S. studies of failures and failure propagation in steam generators
- Review of the Common European R&D programme on the development and propagation of leakage accidents in sodium-heated steam generators
- SNR-300 steam generator accident philosophy - Assessment due to new understandings in Na/H20-reactions
- Design of PFBR steam generator
- Review on steam generator tube failure propagation study in Japan
- EFR-600 MW Straight Tube Steam Generator, the strategy towards the definition of a design basis accident
- Short introduction of the sodium-water steam generator safety program of the USSR
- The experimental and engineering programmes to support the PFR Safety Case following the Superheater 2
under sodium leak: In particular, large scale experiments in the Super Noah Rig at Dounreay
- An analysis of main processes at small water-into-sodium leaks in the BN-350 and BN-600 NPP steam
generators
- The under sodium leak in the PFR Superheater 2 in February 1987
- SWAAM code development, verification and application to steam generator design
- Phenix steam generator Na/H2O reaction incidents
- An algorithm for the determination of emergency process parameters at water-into-sodium leaks in the BN-800
NPP steam generator
- Tests and analysis on steam generator tube failure propagation
- Programme PROPANA: A model of the propagation of water leaks into sodium in steam generators
- MECTUB: A thermomechanical model for overheating studies of LMFBR Steam Generator tubes during a
sodium/water reaction
- Wastage and overheating effects - code development supported by experimental results
- Detection systems of SG tube failure in Monju to limit failure within design basis leak
- Hydrogen detection systems leak response codes
- The UK contribution to the sodium-water reaction R and D programme in support of EFR
- Experimental results of the consequences of sodium water reactions at the bottom tube plate region of straight
tube steam generators
- Test results of sodium-water reaction testing in near prototypical LMR steam generator
|
