A new "designed-for-safety" fast reactor
The design proposed is a compact fast reactor with sodium loop circuits and an auxiliary system for reactor vessel cooling. Each loop includes main piping with freezing valve and fast response stop device, a magnetohydrodynamic (MHD) pump and a shell-type steam generator in which heat exchanging pan...
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| Veröffentlicht in: | Nuclear engineering international 1999-03, Vol.44 (536), p.29-32 |
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| container_title | Nuclear engineering international |
| container_volume | 44 |
| creator | Bobkov, V P Ermolov, N A |
| description | The design proposed is a compact fast reactor with sodium loop circuits and an auxiliary system for reactor vessel cooling. Each loop includes main piping with freezing valve and fast response stop device, a magnetohydrodynamic (MHD) pump and a shell-type steam generator in which heat exchanging panels with activated sodium are separated from steam generating panels by an intermediate cavity. A forced helium circulation is effected in the cavity during reactor operation assuring necessary levels of safety. (Original abstract - amended) |
| format | Magazinearticle |
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| fulltext | fulltext |
| identifier | ISSN: 0029-5507 |
| ispartof | Nuclear engineering international, 1999-03, Vol.44 (536), p.29-32 |
| issn | 0029-5507 2514-4367 |
| language | eng |
| recordid | cdi_proquest_reports_204267478 |
| source | Alma/SFX Local Collection |
| subjects | Accident prevention Compensation Cooling Cooling systems Design Generators Heat exchangers Heat transfer Helium Maintenance Nuclear power plants Nuclear reactor accidents Nuclear reactors Radiation Reactor cores Reactor refueling Sodium Valves |
| title | A new "designed-for-safety" fast reactor |
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