Published 1995 | Version v1
Miscellaneous

Graphite moderator annealing of the experimental reactor for irradiation (0.5 MW)

  • 1. Centro Tecnologico do Exercito, Rio de Janeiro, RJ (Brazil). Instituto de Projetos Especiais

Description

This work describes an operational procedure for the annealing of the graphite moderator in the 0,5 MW Experimental Reactor for Irradiation. A theoretical methodology has been developed for calculating the temperature field during the annealing process. The equations for mass, momentum, and energy conservation for the coolant as well as for the energy conservation in the moderator are solved numerically. The energy stored in the graphite and released in the annealing is accounted for by the use of a modified source term in the energy conservation equation for the moderator. A good agreement has been found for comparisons of the calculations with annealing data from the BEPO reactor. The major parameters affecting annealing have also been determined. (author). 8 refs, 11 figs

Part of:
Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics

Additional details

Additional titles

Original title (Portuguese)
Recozimento do moderador de grafite do reator experimental de irradiacao (0.5MW)

Publishing Information

Imprint Title
Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics
Imprint Pagination
563 p.
Journal Page Range
p. 319-324.

Conference

Title
10. Meeting on Reactor Physics and Thermal Hydraulics.
Original Conference Title
10. Encontro de Fisica de Reatores e Termo-Hidraulica
Dates
7-11 Aug 1995.
Place
Aguas de Lindoia, SP (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
27015002
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ANNEALING; GRAPHITE; IRRADIATION REACTORS; MODERATORS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR PHYSICS; REACTOR SAFETY; REACTOR TECHNOLOGY; REACTORS; RECRYSTALLIZATION; SAFETY ENGINEERING; WIGNER EFFECT
Descriptors DEC
ACCIDENTS; CARBON; ELEMENTS; HEAT TREATMENTS; NONMETALS; REACTOR COMPONENTS; SAFETY

Optional Information

Notes
Imprint:Joint nuclear conference with the 3. Brazilian Meeting on Nuclear Applications.;Anais do 10. Encontro de Fisica de Reatores e Termo-Hidraulica.