1,721,006 research outputs found
Principali risultati delle analisi numeriche relative agli aspetti neutronici, fluidodinamici e termostrutturali del breeding blanket ITER-98 (DDD-FDR)
The Capability of HTRs to Burn Actinides and to Optimize Plutonium Exploitation, Int Conf. ICONE 12, Arlington (USA) April, 2004
Neutronic and thermal mechanical analyses of ITER-FEAT breeding blanket innovative design
Analisi delle soluzioni tecniche attualmente allo studio nei programmi di ricerca Europei e degli Stati Uniti per i reattori a confinamento magnetico, alla luce degli ultimi sviluppi relativi alla riduzione delle dimensioni del progetto ITER
Adaptation of the HCPB DEMO TBM as breeding blanket for ITER:Neutronic and thermal analyses
This paper illustrates a neutronic and thermal analysis of an hypothetical triziogen blanket for ITER made up of modules
similar to the helium cooled pebble bed (HCPB) breeding blanket, which is under studies for the DEMO reactor. Presently
several research centres in Europe are engaged in developing a HCPB module which will be tested in an equatorial port of
ITER. This module, called test blanket module (TBM), is being studied from the neutronic and thermo-mechanical point of
view. The analyses performed by the authors use some results obtained for the HCPB–TBM found in technical literature in
order to assess the implemented model. Moreover, parametric analyses for determining the tritium breeding ratio (TBR) have
been performed for the TBM model as well as for the entire blanket model. The simulations, performed by means of the
Monte Carlo code MCNP-4C, considered different breeder materials (lithium orthosilicate, Li4SiO4 and lithium metatitanate,
Li2TiO3), different values of breeder enrichment in Li6 (between 40% and 90%) and two structural materials (EUROFER and
SiC/SiCf). For ITER, a TBR greater than 1 is obtained using a 90% enriched Li4SiO4 and SiC/SiCf as structural material.
The volumetric heat fluxes obtained by the neutronic analyses have been used for determining the temperature distribution in
the elementary unit of the TBM (breeder unit) and in the correspondent cell of the ITER blanket, subjected to the maximum
neutronic flux. The maximum temperatures of the structural materials were lower than the allowable limits in both the examined
cases
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