Calculation methodology of the thermal margin in the CAREM 25 reactor
Creators
- 1. Investigacion Aplicada SE (INVAP), San Carlos de Bariloche (Argentina)
Description
According to the nuclear reactors characteristics, can be found different methodologies to appraise the thermal margin available in the core. In the particular case of the CAREM (25 MWe) reactor, where the core is cooled by low mass flux and there are zones with positive steam quality, such evaluation is critical. Due to these characteristics, it was necessary to develop one proper methodology. In the present work, the different steps of that development are described: the election of figures of merit for measure the thermal margin, the hypothesis to use, the election of the critical heat flux prediction model, model qualification and the specification of the core wide procedure. In each step assume criteria are discussed. (author). 9 refs, 1 tab, 1 fig
Additional details
Additional titles
- Original title (Spanish)
- Metodologia de calculo del margen termico en el reactor CAREM 25
Publishing Information
- Imprint Title
- Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics
- Imprint Pagination
- 563 p.
- Journal Page Range
- p. 91-96.
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
- 27014967
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNOUT; CRITICAL HEAT FLUX; FUEL CHANNELS; HEAT FLUX; HEAT TRANSFER; HOT CHANNEL; HOT CHANNEL FACTOR; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR PHYSICS; REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY TRANSFER; REACTOR CHANNELS; REACTOR COMPONENTS
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.