Published 2018 | Version v1
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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]

  • 1. GEN IV International Forum (Country Unknown)

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''

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Part of:
Seventh Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors. Presentations

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