Published 2002 | Version v1
Computer medium

Thermal analysis of the fluidized bed nuclear reactor

  • 1. Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica. Dept. de Fisica
  • 2. Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Dept. de Engenharia Nuclear

Description

The fluidized bed nuclear reactor is suggested as a IV generation nuclear reactors. This reactor concept has characteristics of inherent safety and passive cooling. A heat transfer analysis on the spherical fuel element, without phase change, was made. The critical heat flux was evaluated and compared with mean heat flux of the core, in normal operation condition. The optimized power density for operational flow velocity of the coolant was found. It is found that the reactor can operate at much higher power density than the ordinary pressurized water reactor. (author)

Part of:
Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications

Additional details

Additional titles

Original title (Portuguese)
Analise termica do reator nuclear a leito fluidizado
Augmented title (English)
inherent safety; passive cooling

Publishing Information

Imprint Title
Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
Imprint Pagination
[3080 p.]
Journal Page Range
[6 p.]

Conference

Title
International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
Acronym
INAC 2002
Dates
11-16 Aug 2002
Place
Rio de Janeiro, RJ (Brazil)

Optional Information

Notes
5 refs., 1 fig., 2 tabs., 7 graphs Imprint:Published only in CD-Rom