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Conference

Post-dryout heat transfer in sodium-cooled fast reactors

  • Authors : Pedersen, D

  • Source: Conference: 7. international heat transfer conference, Munich, F.R. Germany, 6 Sep 1982

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Report

EFFECT OF HYDRAULIC PROBLEMS ON THE DESIGN OF SODIUM-COOLED FAST REACTORS

  • Authors : Lambert, P

  • Source: Conference: Colloquium on the development of the technology of sodium-cooled reactors, Monaco, 23-27 Mar 1970

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Conference

Overview of the use of ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant

  • Authors : Shieh, A

  • Source: Conference: 8th International Conference on Nuclear Engineering (ICONE-8), Baltimore, MD (US), 04/02/2000--04/06/2000; Other Information: PBD: 2 Apr 2000

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Conference

Integrated intra-subassembly treatment in the SASSYS-1 LMR systems analysis code

  • Authors : Dunn, F

  • Source: Conference: International topical meeting on reactor thermal hydraulics: towards the next generation of nuclear power plants, Salt Lake City, UT (United States), 20-24

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Conference

SAS4A analysis of unprotected loss of flow accidents in a metal fuel reactor

  • Authors : Tentner, A

  • Source: Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL

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Conference

Thermal analysis of the FSP-1 fuel pin irradiation test

  • Authors : Lyon, III, W

  • Source: Conference: 8. symposium on space nuclear power systems, Albuquerque, NM (USA), 6-10 Jan 1991

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Conference

Dynamic effect of sodium-water reaction in fast flux test facility power addition sodium pipes

  • Authors : Anderson, M

  • Source: Conference: Pressure vessels and piping conference: be in tune for the 90's, Nashville, TN (USA), 17-21 Jun 1990

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Conference

Fast Flux Test Facility core restraint system performance

  • Authors : Trenchard, R

  • Source: Conference: International conference on fast reactor core and fuel structural behavior, Inverness (UK), 4-6 Jun 1990

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Conference

Thermal-hydraulic impact of failure of highly irradiated fuel pins on LMR passive safety

  • Authors : Herzog, J

  • Source: Conference: American Nuclear Society winter meeting, Washington, DC (USA), 11-15 Nov 1990

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