Published 1999
| Version v1
Miscellaneous
Experimental circuit for research on emergency cooling systems of advanced reactors
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)
Description
This paper describes the project and presents the first results of temperature distribution and flow estimates of the Circuit of Natural Circulation developed at the Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP, inside of the Project of the Diretoria de Pesquisa e Desenvolvimento of CNEN entitled Amplification and Complementation of the Experimental Facilities of Passive Systems of Advanced Reactor. The objective of that project was adapt the experimental facilities of the Institutions that began research lines in Advanced PWR Reactors. The results obtained show that the circuit is well adapted for the purposes of research of passive emergency cooling systems. (author)
Availability note (English)
Available from the library of the Brazilian Nuclear Energy Commission, Rio de JaneiroAdditional details
Additional titles
- Original title (Portuguese)
- Circuito experimental para pesquisa de sistemas de resfriamento de emergencia de reatores avancados
Publishing Information
- Imprint Pagination
- 7 p.
Conference
- Title
- 7. General congress on nuclear energy
- Original Conference Title
- 7. Congresso geral de energia nuclear
- Dates
- 31 Aug - 3 Sep 1999
- Place
- Belo Horizonte, MG (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 30041785
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BRAZILIAN CNEN; DATA ACQUISITION SYSTEMS; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; SECONDARY COOLANT CIRCUITS; TEMPERATURE DISTRIBUTION
- Descriptors DEC
- BRAZILIAN ORGANIZATIONS; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MASS TRANSFER; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 6 figs.; e-mail: bdbfilho at net.ipen.br