Published 2010
| Version v1
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Impact of Fast Reactors Operating Experience on PFBR Design to Enhance Safety
Description
Summary of LMFBR Operating Experience • ∼400 reactor year operating experience of experimental and demonstration reactors available. • Corrosion of structural materials in reactor grade sodium is negligible. • Performance of SS 304 and 316 type grades excellent. Performance of SS 321 and low Alloy Steel 15 Mo3 poor. • Performance of elevated temperature components satisfactory indicating creep fatigue damage can be well taken care of. • Excellent performance of mixed oxide fuel up to moderately high burnup levels influenced by clad and wrapper materials. • IHX performance except for Phenix reactor is excellent. Failure of Phenix secondary sodium outlet header is well understood.
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49104072.pdf
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Additional details
Identifiers
Publishing Information
- Imprint Title
- First Joint IAEA-GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors. Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 13 p.
- Report number
- INIS-XA--18M4855
Conference
- Title
- 1. Joint IAEA-GIF Workshop on Operational and Safety Aspects of Sodium Cooled Fast Reactors
- Dates
- 23-25 Jun 2010
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49104072
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUILDING MATERIALS; LMFBR TYPE REACTORS; LOW ALLOY STEELS; MIXED OXIDE FUELS; SODIUM
- Descriptors DEC
- ALKALI METALS; ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; SOLID FUELS; STEELS; TRANSITION ELEMENT ALLOYS