LOMONACO , Guglielmo

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A revised textbook gives an up-to-date overview of the nuclear fuel cycle from mining to radioactive waste disposal. Aimed at nonspecialists, it looks to be a suitable replacement for some of the older classical texts on this topic.

Nuclear safety, nuclear security and nuclear safeguards regimes have not historically developed at the same pace and surely have not reached the same level of maturity. Nevertheless, these aspects are of special relevance in the current global nuclear energy context when considering the numerous countries that have and will have the legitimate...

This chapter looks at Generation IV nuclear reactors, such as the very high-temperature reactor (VHTR), the supercritical water reactor (SCWR), the molten salt reactor (MSR), the sodium-cooled fast reactor (SFR), the lead-cooled fast reactor (LFR) and the gas-cooled fast reactor (GFR). Reactor designs and fuel cycles are also described.

The corrosion issues in high temperature reactors (HTRs) are probably less critical compared to such issues in other nuclear reactors. Nevertheless it is important to take them into account adequately. In this chapter we consider the following items: structural metallic material corrosion in high temperature conditions; graphite corrosion...

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This review article is an overview on some recent developments of Generation IV (GEN-IV) gas cooled nuclear reactor performing in the frame of innovative symbiotic fuel cycle mainly by our research group. In fact such reactors, in addition to energy generation, can also improve nuclear fuel exploitation and decrease nuclear waste radiotoxicity...

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In the recent past the so-called GCFR has been again a subject of study by the international scientific community. This type of reactors, although still in a preliminary stage of development, is a very interesting perspective because combines the positive characteristics common to all the fast reactors with those of the reactors cooled by...

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This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gas-cooled fast reactor (GFR)-like configuration. Particularly, it shows a comparison between the two Monte Carlo-based codes, each one adopting three different cross-section data sets, namely, JEFF-3.1, JEFF-3.1.2, and...

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Portale dell'Ingegneria Energetica e Nucleare

Pubblicato sul Portale dell'Ingegneria Energetica e Nucleare

Pubblicato sul Portale dell'Ingegneria Energetica e Nucleare

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The pebble bed gas-cooled reactor is one of the most promising concepts among the Generation III and Generation IV reactors. Currently, the pebble bed modular reactor (PBMR) design, both U and Pu and minor actinide fueled, is being developed. Modeling the arrangement of coated particles (CPs) inside a spherical region like a pebble seems to be...

Preliminary analyses already performed showed that innovative GCRs, both thermal and fast, are very promising candidate to reach the Gen-IV sustainability goal. The integrated LWR-HTR-GCFR basically aims at closing the current nuclear fuel cycle: in principle, thanks to the unique characteristics of Helium coolant reactors, LWR SNF along with...

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The present paper reports a numerical investigation of a forced convection water flow within a two-dimensional ribbed channel. A uniform heat flux is applied on the external walls. The flow regime is turbulent and Reynolds numbers are in the range 10·10^3÷100·10^3. Square and chamfered rib shapes with different arrangements are analyzed in...