Published 1982
| Version v1
Miscellaneous
Open
Nondestructive analysis of uranium mass in MTR fuel elements
Creators
- 1. Instituto de Pesquisas Energeticas e Nucleares, Sao Paulo (Brazil). Centro de Engenharia Nuclear
Description
Results of uranium mass non destructive analysis by the pulsed source technique, are presented. The method used is that of relate measurement, being that the uranium mass is determined by the measurement of the delayed neutron production, emited after fissions, produced by sample irradiated with pulses of 14 MeV neutrons. Three types of samples were analysed: metallic uranium disks, sintered pellets of uranium dioxide and plates of uranium-alluminium alloys, surrounded by an alluminium coat. Those plates simules the fuel elements for MTR type reactor. The result of the measurements are reproducible in the range of 1.6 to 3.9%. The errors in a specified measure depends on the form, size and mass of the sample. (E.G.)
Abstract (Portuguese)
Apresentam-se resultados da analise nao destrutiva da massa de uranio natural atraves da tecnica de fonte pulsada. O metodo empregado e o de medida relativa, sendo que a massa de uranio e determinada atraves da medida da producao de neutrons atrasados, emitidos apos fissoes produzidas pela irradiacao da amostra com pulsos de neutrons de energia aproximadamente igual a 14 MeV. Tres tipos de amostras foram analisadas, a saber: discos de uranio metalico, pastilhas sinterizadas de oxido de uranio e placas de liga uranio-aluminio, envoltas por uma camada de aluminio. Essas placas simulam aquelas de elementos combustiveis de reator tipo MTR (Material Testing Reactor). Os resultados das medidas sao reprodutiveis dentro do intervalo de 1,6 a 3,9%. O erro numa medida especifica depende da forma, tamanho e massa da amostra. (Autor)Files
14807268.pdf
Files
(442.0 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:6a4ecea17c0f5710357cc2234092cf52
|
442.0 kB | Preview Download |
Additional details
Additional titles
- Original title (Portuguese)
- Analise nao destrutiva da massa de uranio em elemento combustivel de reator tipo MTR
Publishing Information
- Imprint Title
- 3. National Meeting of Reactor Physics
- Imprint Pagination
- 570 p.
- Journal Page Range
- p. 403-412.
- Report number
- INIS-BR--95
Conference
- Title
- 3. National Meeting of Reactor Physics.
- Dates
- 12-14 Dec 1982.
- Place
- Itaipava, RJ (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 14807268
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; FUEL ELEMENTS; MTR REACTOR; NONDESTRUCTIVE ANALYSIS; PULSED NEUTRON TECHNIQUES; URANIUM; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; CHEMICAL ANALYSIS; ELEMENTS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; METALS; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:3. Encontro Nacional de Fisica de Reatores.