Rivogliamo il nucleare?

[Malik]

Favorevole

[Medsim]

Sei tu che hai posto il quesito ed io ti ho risposto che:
non mi sembra che ci sia un dibattito politico così intenso su questo tema...

Oppure a te sembra che il centro-destra abbia posto questo problema seriamente e decisamente all'ordine del giorno?

Dovrebbe essere un problema che diventi all'ordine del giorno per il cdx.
La produzione energetica e la capacità della nostra nazione di raggiungere la tanto agognata autonomia negli approvvigioanmienti di eletrticità è un passo fondamentale per il rilancio della nostra economia.

[cangaru']

Energia nucleare: realtà e prospettive

Nuclear energy: reality and perspectives

Abstract

For the just started XXI century, a scenery .............

se ci mettessi il link forse potremmo fare dei nostri commenti personali

[cangaru']

Dovrebbe essere un problema che diventi all'ordine del giorno per il cdx.

ma nessuno ne parla

[Medsim]

Avrai occupato 10 M di spazio con sta roba che tanto nessuno leggerà.

Sono cmq CERTO che nessuno permetterà che una centrale nucleare venga costruita sul proprio territorio, quindi il discorso non ha neppure senso.

Io sono pronto a qualunque cosa pur di impedire che una centrale sia costruita vicino a me.

Il discorso dei luoghi su cui realizzare i suddetti impianti è da valutare con attenzione, andranno fatte le debite V.I.A. e fatta una corretta campagna di informazione sui reali rischi.

[Medsim]

ma nessuno ne parla

Purtroppo è vero, ma non sarà sempre così.

[maimaria]

Dovrebbe essere un problema che diventi all'ordine del giorno per il cdx.
La produzione energetica e la capacità della nostra nazione di raggiungere la tanto agognata autonomia negli approvvigioanmienti di eletrticità è un passo fondamentale per il rilancio della nostra economia.

Purtroppo per te i politici (compresi quelli del centro-dx) non la pensano così. Mi sembra un'ipotesi fuori dalla realtà (cittadini e politici), se non per alcuni.

[Ronnie]

http://hid.casaccia.enea.it/ENuc-Math.htm

questo è l'articolo che campeggia in prima pagina.

[Oli]

Il discorso dei luoghi su cui realizzare i suddetti impianti è da valutare con attenzione, andranno fatte le debite V.I.A. e fatta una corretta campagna di informazione sui reali rischi.

SI si, che facciano le via, le facciano bene, ne facciano 50, le paghino 50.000.000 o più, tanto la gente del luogo non permetterà mai la costruzione di quei mostri.

[Zmajcek]

Naturalmente a favore.

Aggiungo ancora un breve intervento sui reattori veloci, che forniranno combustibile quando il prezzo dell' uranio supererà i livelli di economicità che rendono il nucleare conveniente rispetto ad altre fonti.

FAST NEUTRON REACTORS

Several countries have research and development programs for improved Fast Breeder Reactors (FBR), which are a type of Fast Neutron Reactor. These use the uranium-238 in reactor fuel as well as the fissile U-235 isotope used in most reactors.

About 20 liquid metal-cooled FBRs have already been operating, some since the 1950s, and some supply electricity commercially. About 290 reactor-years of operating experience have been accumulated.

Natural uranium contains about 0.7 % U-235 and 99.3 % U-238. In any reactor the U-238 component is turned into several isotopes of plutonium during its operation. Two of these, Pu-239 and Pu-241, then undergo fission in the same way as U-235 to produce heat. In a fast neutron reactor this process is optimised so that it can 'breed' fuel, often using a depleted uranium blanket around the core. FBRs can utilise uranium at least 60 times more efficiently than a normal reactor. They are however expensive to build and could only be justified economically if uranium prices were to rise to pre-1980 values, well above the current market price.

For this reason research work on the 1450 MWe European FBR has almost ceased. aClosure of the 1250 MWe French Superphenix FBR after very little operation over 13 years also set back developments. Research continues in India. At the Indira Gandhi Centre for Atomic Research a 40 MWt fast breeder test reactor has been operating since 1985. In addition, the tiny Kamini there is employed to explore the use of thorium as nuclear fuel, by breeding fissile U-233. In 2004 construction of a 500 MWe prototype fast breeder reactor started at Kalpakkam. The unit is expected to be operating in 2010, fuelled with uranium-plutonium carbide (the reactor-grade Pu being from its existing PHWRs) and with a thorium blanket to breed fissile U-233. This will take India's ambitious thorium program to stage 2, and set the scene for eventual full utilisation of the country's abundant thorium to fuel reactors.

Japan plans to develop FBRs, and its Joyo experimental reactor which has been operating since 1977 is now being boosted to 140 MWt. The 280 MWe Monju prototype commercial FBR was connected to the grid in 1995, but was then shut down due to a sodium leak.

The Russian BN-600 fast breeder reactor has been supplying electricity to the grid since 1981 and has the best operating and production record of all Russia's nuclear power units. It uses uranium oxide fuel and the sodium coolant delivers 550°C at little more than atmospheric pressure The BN-350 FBR operated in Kazakhstan for 27 years and about half of its output was used for water desalination. Russia plans to reconfigure the BN-600 to burn the plutonium from its military stockpiles.

Construction has started at Beloyarsk on the first BN-800, a new larger (880 MWe) FBR from OKBM with improved features including fuel flexibility - U+Pu nitride, MOX, or metal, and with breeding ration up to 1.3. It has much enhanced safety and improved economy - operating cost is expected to be only 15% more than VVER. It is capable of burning 2 tonnes of plutonium per year from dismantled weapons and will test the recycling of minor actinides in the fuel.

Industry spokesmen have warned the government that Russia's world leadership in FBR development is threatened due to lack of funding for completion of BN-800.

Russia has experimented with several lead-cooled reactor designs, and has used lead-bismuth cooling for 40 years in reactors for its 7 Alfa class submarines. Pb-208 (54% of naturally-occurring lead) is transparent to neutrons. A significant new Russian design is the BREST fast neutron reactor, of 300 MWe or more with lead as the primary coolant, at 540°C, and supercritical steam generators. It is inherently safe and uses a high-density U+Pu nitride fuel with no requirement for high enrichment levels. No weapons-grade Pu can be produced (since there is no uranium blanket - all the breeding occurs in the core). The initial cores can comprise Pu and spent fuel. Subsequently, any surplus Pu can be used as the cores of new reactors. Spent fuel can be recycled indefinitely, with on-site reprocessing and associated facilities. A pilot unit is being built at Beloyarsk and 1200 MWe units are planned.

In the USA, GE was involved in designing a modular 150 MWe liquid metal-cooled inherently-safe reactor - PRISM. GE and Argonne have also been developing an advanced liquid-metal fast breeder reactor (ALMR) of over 1400 MWe, but both designs at an early stage were withdrawn from NRC review. No US fast neutron reactor has so far been larger than 66 MWe and none has supplied electricity commercially.

The Super-PRISM is a GE advanced reactor design for compact modular pool-type reactors with passive cooling and decay heat removal. Modules are 1000 MWt and operate at higher temperature - 510°C, than the original PRISM. The pool-type modules contain the complete primary system with sodium coolant. The Pu & DU fuel can be oxide or metal, but minor actinides are not removed in reprocessing so that even fresh fuel is intensely radioactive and hence resistant to misappropriation. The fission products are removed in reprocessing and resultant wastes are shorter-lived than usual. Fuel stays in the reactor six years, with one third removed every two years. The commercial plant concept uses six reactor modules to provide 2280 MWe, and the design meets Generation IV criteria including generation cost of under 3 cents/kWh.


Come si vede numerosi reattori veloci sono stati costruiti al mondo, tra cui sottolineo quello russo, il BN-600 connesso alla rete elettrica già nel 1981.
Altro che solo prototipi caro proteus!