Thermal-hydraulic design of a gas cooled fast reactor

2003 International Congress on Advances in Nuclear Power Plants - Proceedings of ICAPP 2003

Volumn , Issue , 2003, Pages

  Gaillard, J P ^a   Mignot, G ^a   Conti, A ^a  

^a IRFM   (France)

Author keywords

[No Author keywords available]

Indexed keywords

GAS COOLED REACTORS; NATURAL CONVECTION; NUCLEAR ENERGY; NUCLEAR POWER PLANTS;

DECAY HEAT; DECAY HEAT REMOVAL; FAST SPECTRUM; GAS COOLED FAST REACTORS; HEAVY GAS; HELIUM-COOLED REACTORS; THERMAL-HYDRAULIC DESIGNS;

FAST REACTORS;

EID: 84933182737     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. Current status and future development of modular high temperature gas cooled reactor technology, chapter 3 and 4, IAEA-TECDOC-1198, Vienna (2001).
2. J. C. GARNIER & al, Preliminary design of an advanced gas cooled fast reactor - Cores, Fuel, Forms and primary system concepts," ICAPP 03, Cordoba, Spain (2003).
3. G. Melese and R. Katz, Thermal and flow design of Helium-Cooled Reactors, pp 353-357, ANS, La Grange Park, Illinois USA (1984).
4. A. Hoffmann, A. Combescure, CASTEM (CEA SEMT): A System of Finite Element Computer Programs, paper 40 presented at Conference on "Structural Analysis, Design and Construction in Nuclear Power Plant, Porto Alegre, Brazil, 1978