Published 2018
| Version v1
Miscellaneous
Open
Safety Design Guidelines (SDG) on Safety Approach and Design Conditions for Generation-IV Sodium-cooled Fast Reactor System [7. Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors]
Description
Scope of SDG on Safety Approach: • This report is intended to provide recommendations and guidance on how to comply with the GIF SFR Safety Design Criteria. It presents examples for the measures stated in criteria as the best practices to help the designers achieve high levels of safety. • Initially, the guidelines will focus on specific safety concerns, such as reactivity characteristics of SFRs and heat removal issues. • To address the potential consequences of such accidents, this report focuses on providing examples of design approaches for ''prevention and mitigation of severe accidents'' and for ''loss-of-decay heat removal capability as a situation that needs to be practically eliminated''
Files
49059962.pdf
Files
(1.4 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:a682bb847f0fe00e0da6724da8568439
|
1.4 MB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Seventh Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 32 p.
- Report number
- INIS-XA--18M2236
Conference
- Title
- 7. Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors
- Dates
- 27-29 Mar 2018
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059962
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; FAST REACTORS; REACTIVITY; REACTIVITY COEFFICIENTS; REACTOR DESIGN; REACTOR SAFETY; RECOMMENDATIONS; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS; SEVERE ACCIDENTS; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; DESIGN; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; SAFETY
Optional Information
- Secondary number(s)
- IAEA-I3-TM--52248