Conveners
3.4 Sodium leak/fire and other safety issues
- Yasushi OKANO (Japan Atomic Energy Agency)
- IURII SHVETSOV (Private institution «Innovation and technology center for the «PRORYV» project»)
Mr
Olga Myazdrikova
(Leypunsky Institute for Physics and Power Engineering (IPPE))
6/27/17, 1:30 PM
Track 3. Fast Reactor Safety
ORAL
On the basis of the normative documents requirements on fire safety of nuclear power facilities the build concept and the composition of fire protective system in fast reactors premises with sodium equipment are presented. The main purpose of sodium fire safety system is to protect the technological areas of nuclear power plants with sodium cooled fast reactors from hazards of sodium fire. The...
Dr
Mitsuhiro Aoyagi
(Japan Atomic Energy Agency)
6/27/17, 1:50 PM
Track 3. Fast Reactor Safety
ORAL
Since sodium has high chemical reactivity with oxygen and moisture, sodium fire accident is one of key issues in sodium-cooled fast reactor (SFR) plants when the sodium leaks out of a coolant circuit. In order to evaluate the consequence of the sodium fire event numerically, JAEA has developed sodium fire analysis codes such as SPHINCS and AQUA-SF. This paper describes a PIRT (Phenomena...
Dr
Luke Lebel
(Institut de Radioprotection et de Sûreté Nucléaire)
6/27/17, 2:10 PM
Track 3. Fast Reactor Safety
ORAL
The original sodium fast reactor concepts date back to the 1950s and 1960s, and there were large programs in France, Japan, Russia, and the United States in the 1970s and 1980s to design and build commercial-scale SFRs. Many of these programs were abandoned in the 1990s, but a considerable amount of work was done prior to that in order to demonstrate the concepts, and to support the safety...
Mr
Marti Jeltsov
(KTH Royal Institute of Technology)
6/27/17, 2:30 PM
Track 3. Fast Reactor Safety
ORAL
Pool-type configuration of LFR (lead-cooled fast reactor) primary systems allows for simple and economic reactor design solutions. However, partially-filled heavy liquid pools pose seismic safety concerns related to sloshing. Violent sloshing can lead to structural failures, gas entrapment and potential core voiding. Seismic isolation systems are used to reduce the mechanical stresses in...
Mr
Kazuo YOSHIMURA
(Japan Atomic Energy Agency)
6/27/17, 2:50 PM
Track 3. Fast Reactor Safety
ORAL
To maintain sodium level inside reactor vessels above cores is essential to keep core-cooling for sodium leakage accidents in loop-type sodium-cooled fast reactors. In the loop-type prototype fast reactor Monju which has three primary heat transport systems (PHTSs), a single coolant leakage accident in a PHTS has been taken into account as a design basis accident (DBA). On the other hand, it...
