Published 1990 | Version v1
Miscellaneous Metadata-only

Test for check the integrity of the IEA-R1 reactor fuel element cladding

Creators

  • 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)

Description

This paper describes an experimental method for verifying the integrity of the fuel element cladding used in reactor core arrangement. The experimental method allows an analysis of fuel element behavior with respect to the fission products release and provides a criteria for rejection or approval of the fuel element. (author)

Additional details

Additional titles

Original title (Portuguese)
Ensaios para verificacao da integridade da camisa dos elementos combustiveis utilizados no reator IEA-R1

Publishing Information

Imprint Title
Proceedings of the 3. General Congress on Nuclear Energy. v. 6
Imprint Pagination
185 p.
Journal Page Range
p. 38-43.

Conference

Title
3. General Congress on Nuclear Energy.
Dates
22-27 Jul 1991.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
23087320
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; FISSION PRODUCTS; FUEL ELEMENTS; IEAR-1 REACTOR; TESTING
Descriptors DEC
DEPOSITION; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SURFACE COATING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Anais do 3. Congresso Geral de Energia Nuclear. v. 6.