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
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.