Safety Design of Advanced Loop Type SFR
Creators
- 1. Japan Atomic Energy Agency (JAEA), Advanced Fast Reactor Cycle System R&D Center (Japan)
Description
Summary: • To achieve safety goals for Generation IV reactor, design measures should be taken under severe plant conditions including those for external events considering the lessons learned from the Fukushima Dai-ichi NPPs accident. • Advanced loop type SFR, JSFR, design concept has been updated with emphasis on the design measures against severe external events and loss of heat removal type events (LOHRS) after reactor shutdown. ◆ Design measures for various external events such as earthquake, tsunami, strong wind, snow pack and fire are taken into account in the design of reactor components and reactor building with certain margin. ◆ In order to practically eliminate core uncovered situation or total loss of heat removal, additional design measures, e.g., application of accident management, alternative cooling system are introduced.
Files
49059958.pdf
Files
(1.7 MB)
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Additional details
Publishing Information
- Imprint Title
- Sixth Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 19 p.
- Report number
- INIS-XA--18M2223
Conference
- Title
- 6. Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors
- Dates
- 14-15 Nov 2016
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059958
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; AFTER-HEAT REMOVAL; EARTHQUAKES; FAST REACTORS; FIRE PREVENTION; NUCLEAR POWER PLANTS; REACTOR COOLING SYSTEMS; REACTOR DESIGN; REACTOR SAFETY; REACTOR SHUTDOWN; SAFETY ANALYSIS; SODIUM COOLED REACTORS; TSUNAMIS
- Descriptors DEC
- COOLING SYSTEMS; DESIGN; ENERGY SYSTEMS; EPITHERMAL REACTORS; GRAVITY WAVES; LIQUID METAL COOLED REACTORS; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; SAFETY; SEISMIC EVENTS; SHUTDOWN; THERMAL POWER PLANTS; WATER WAVES
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-52279