Published 1990 | Version v1
Miscellaneous Metadata-only

Thermohydraulic tests in the area of reactor safety done in CDTN

Creators

  • 1. Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil)

Description

The main experimental works performed in the last five years at the Thermohydraulics Laboratory of the Nuclear Technology Development Center, in the field of reactor safety are briefly described. This paper cover the performing and analysis of pressure drop, heat transfer and mixing tests in 3X3 rod bundle and rewetting tests in single tube section. (autor)

Availability note (English)

Available from the Library of the Comissao Nacional de Energia Nuclear, RJ, Brazil.

Abstract (Portuguese)

Descrevem-se de forma sucinta os principais trabalhos realizados nos ultimos cinco anos, na area de Seguranca de Reatores, no Divisao de Termohidraulica do Centro de Desenvolvimento da Tecnologia Nuclear. Este artigo aborda a realizacao e analise de testes de perda de carga, transferencia de calor e mistura entre subcanais realizados em secao de testes com geometria em feixe 3x3 e testes de remolhamento em secao tubular. (autor)

Additional details

Additional titles

Original title (Portuguese)
Testes termohidraulicos na area de seguranca de reatores realizados no Centro de Desenvolvimento da Tecnologia Nuclear

Publishing Information

Imprint Pagination
10 p.

Conference

Title
3. General Brazilian Congress of Nuclear Energy.
Dates
22-27 Jul 1990.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
21090525
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BRAZILIAN CNEN; FLUID FLOW; HEAT TRANSFER; PRESSURE DROP; PWR TYPE REACTORS; REACTOR SAFETY
Descriptors DEC
BRAZILIAN ORGANIZATIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS