Published 1983 | Version v1
Miscellaneous Metadata-only

Thermohydraulics tests in mock-up of nuclear fuel

Creators

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

Description

The main experimental works performed in the Thermohydraulics Laboratory of the NUCLEBRAS Nuclear Technology Development Center, in the field of thermofluodynamics are briefly described. These works include the performing of steady-state flow tests in single tube test sections, and the design and construction of a rod bundle test section, which will be also used for those kind of tests. Mention is made of the works to be performed in the near future, related to steady-state and transient flow tests. (Author)

Abstract (Portuguese)

Descrevem-se de forma sumaria os principais trabalhos experimentais ja realizados, na area de termofluodinamica, no Laboratorio de Termohidraulica do Centro de Desenvolvimento da Tecnologia Nuclear, da NUCLEBRAS. Estes trabalhos incluem a realizacao de testes em regime estacionario utilizando secoes de testes tubulares, e o projeto e construcao de uma secao de testes em feixe, tambem destinada a testes desta natureza. E feita referencia aos trabalhos a se realizarem em futuro proximo, relativos a testes em regimes permanente e transitorio. (Autor)

Additional details

Additional titles

Original title (Portuguese)
Testes termohidraulicos em maquetes de elemento combustivel nuclear

Publishing Information

Imprint Title
Proceedings of the 7. Brazilian Congress on Mechanical Engineering. v. A
Imprint Pagination
615 p.
Journal Page Range
v. A p. 173-182.
Report number
INIS-BR--349

Conference

Title
7. Brazilian Congress on Mechanical Engineering.
Dates
13-16 Dec 1983.
Place
Uberlandia, MG (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
16072077
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLUID FLOW; FUEL ELEMENTS; HEAT TRANSFER; MOCKUP; PWR TYPE REACTORS; SIMULATION; TESTING
Descriptors DEC
ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 7. Congresso Brasileiro de Engenharia Mecanica. v. A.