Published 1995 | Version v1
Miscellaneous

Calculation methodology of the thermal margin in the CAREM 25 reactor

  • 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

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

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.