Published 2014
| Version v1
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Fourth Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors. Presentations
Description
The main purpose of the fourth Joint GIF – IAEA Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors was to present and discuss the following topics: - Status of the SDCSFR Phase 1 Report review by national Regulators and International Organizations (IAEA, NEA, MDEP); - Implementation of current SDCSFR by the designers of innovative SFRs concepts: examples of designers' engineering solutions to SFR safety design criteria; - Status of SFRSDC Phase 2 development: design criteria quantification, development of detailed guidelines to implement general criteria; - Technical discussion on specific safety design criteria: practical elimination of accident situations, design extension conditions, sodium void reactivity effect.
Availability note (English)
Also available on-line: https://www.iaea.org/NuclearPower/Meetings/2014/2014-06-10-06-11-TM-NPTD.htmlFiles
49059900.pdf
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Additional details
Publishing Information
- Imprint Pagination
- vp.
- Report number
- INIS-XA--18K5269
Conference
- Title
- 4. Joint IAEA-GIF Technical Meeting/Workshop on Safety of Sodium-Cooled Fast Reactors
- Dates
- 10-11 Jun 2014
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49059900
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- FAST REACTORS; IAEA; IMPLEMENTATION; LEADING ABSTRACT; MEETINGS; NEA; REACTOR ACCIDENT SIMULATION; REACTOR DESIGN; REACTOR SAFETY; RECOMMENDATIONS; SAFETY ANALYSIS; SAFETY ENGINEERING; SODIUM COOLED REACTORS; VOID COEFFICIENT; VOIDS
- Descriptors DEC
- ABSTRACTS; DESIGN; ENGINEERING; EPITHERMAL REACTORS; INTERNATIONAL ORGANIZATIONS; LIQUID METAL COOLED REACTORS; OECD; REACTIVITY COEFFICIENTS; REACTOR LIFE CYCLE; REACTORS; SAFETY; SIMULATION
Optional Information
- Secondary number(s)
- IAEA--622-I3-TM-47191