Safety improvement research to design a sodium fast reactor steam generator with regard to sodium/water reaction risk

International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010

Volumn 1, Issue , 2010, Pages 667-680

  Gerber, A ^a   Pirus, J P ^a   Beils, S ^a   Carluec, B ^a   Beauchamp, F ^b   Jeannot, J Ph ^b   Prele G ^c  

^a AREVA NP   (France)

^b IRFM   (France)

^c EDF R AND D   (France)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT CONDITIONS; ELECTRICITY PRODUCTION; FAST DYNAMICS; MITIGATION MEASURES; MITIGATION SYSTEMS; POTENTIAL BENEFITS; SAFETY IMPROVEMENT; SECONDARY LOOPS; SECONDARY SYSTEM; SODIUM COOLED FAST REACTOR; SODIUM FAST REACTORS; SODIUM-WATER REACTION; SODIUM-WATER REACTION PHENOMENON; TUBE BUNDLE; WATER LEAK DETECTION; WATER-STEAM CYCLE;

CHEMICAL REACTIONS; FAST REACTORS; LEAK DETECTION; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; SODIUM; STEAM; STEAM ENGINEERING; STEAM GENERATORS;

DESIGN;

EID: 77956219937     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (5)

1. RCC-MR Code, Design and Construction rules for Mechanical components of FBR nuclear islands, AFCEN, 2007.
2. th Int. Conf. on Structural Mechanics in reactor Technology (SMiRT 13), Porto Alegre, Brazil, August 13-18,1995.
3. SRIDHARAN R. and al, "An electrochemical hydrogen meter for measuring hydrogen in sodium using a ternary electrolyte mixture," in Journal of Nuclear Materials, 312, 2003, pp. 10-15.
4. JEANNOT JPh, GNANASEKARAN T. and al., "In-sodium hydrogen detection in the Phenix fast reactor steam generator: a comparison between two detection methods (May 2009) " N267, Proceeding of ANIMMA International Conference, 7-10 June 2009, France.
5. NEMRODW software: see http://www.nemrodw.com.