Reattori nucleari di nuova generazione
Nuclear reactor systems cooled by lead-bismuth eutectic (LBE) are subject to a number of
serious problems, namely:
corrosion, erosion and mass transfer;
radioactive safety problem, particularly due to the Po produced with the reaction:
209 210 210
Bi (n,γ) Bi Po (its half life of 138 days poses an operational, rather than a
− thermohydrodinamic problems;
− environmental concern, since lead and bismuth are heavy metal requiring adequate
− separation from the environment. When irradiated, they represent a “mixed” waste which
further complicates disposal.
Major research efforts are at present underway in many laboratories to address these issues.
The corrosion issue affecting the vessel integrity is a major one. A protective film consisting
of oxide compounds of steel components is claimed as an adequate measure . The basis of the
film would be Fe O . The reliability of such a solution needs to be verified, recalling the
experience in metal cooled reactors of not negligible oxide layer detachments, in presence of
power/temperature transients (and, in the case of an ADS, also in presence of spallation
products, if the coolant serves also as target).
On the other hand, LBE as coolant has a number of advantages, among which, relatively to
the impossibility of explosion and fire at interaction with air, water and vapor, due to the
− low chemical lead and bismuth activity;
the impossibility of the coolant boiling out, due to the high boiling point of Pb-Bi
its enhanced ability (with respect to sodium) of transmuting long lived fission products,
such as Tc , in case this is a strategy to be adopted. This ability stems from the relatively
small neutron lethargy loss per collision associated with the PBE coolant, which allows
neutrons to remain longer after many collisions within the capture resonance width ranges
of those isotopes;
superior properties for natural convection cooling;
− the possibility of increased efficiency, due to the ability of liquid Pb-Bi to support higher
− thermal efficiencies due to the high boiling temperature (temperature limits associated
with the corrosion issue may however limit its operating value);
transport cross section of Pb ~2 ÷3 times larger than that for Na, (although its capture
− cross section is ~5 ÷10 times larger than that, relatively small, of Na). Besides, the Pb
atom density is 40% higher than for Na. As a consequence, the neutron economics in
presence of the Pb coolant are better: lower fissile loading which in turn entails higher
breeding and, consequently, smaller reactivity swing;
5 Yu. I. Orlov , "Stages of development of Lead-Bismuth as a coolant for nuclear reactors in Russia", MIT ATW Technical
Review Meeting, 1998, Boston, Jan. 15-1998. 5
retention of most actinides and fission products if released into the coolant after an
− accidental event.
Sodium is the best known metal coolant for fast reactors. A main advantage is its
compatibility with all the materials to be used for fabrication of fuel cladding, reactor vessel,
internal components, together with its low pressure of operation.
Strong efforts have been made on the Superphenix reactor to improve the in-service
inspection, which remains an issue (as for other liquid metals). Another drawback is its
chemical reactivity with both air and water.
The use of sodium as coolant would require its physical separation from the spallation
medium, supposed to be Pb-Bi.
Comparison of sodium with lead-bismuth has been done above, when discussing the Pb-Bi
Sodium may be considered a possible back-up solution in case Pb-Bi technology would result
The utilization of gas (helium, or CO ) as coolant has a number of advantages, since it:
facilitates the in-service inspection and repair, as compared to liquid metals;
− allows the operation with fast neutron spectrum, with no adverse reactivity feedback in
− case of voiding as compared to liquid metals;
has a negligible absorption of neutrons. Hence it produces no radiological concern;
− is non-corrosive.
Use of gas, however, requires operating with high internal pressure (typically 50 to 70 bars),
with the related consequences on vessel loading; also, in case of loss of coolant (de-
pressurization), decay heat removal is somehow more troublesome in natural circulation and
would lead to very high temperatures for the fuel, and, correspondingly, for the internal
Gas cooled reactors have been already developed, with thermal neutrons (built and operated)
as well as with fast neutrons (conceptual design stage).
The choice of gas requires a physical separation between the spallation medium and the
primary coolant, with the added constraint that this separation must withstand the loads
(pressure, temperatures) related to the gas. 6
Traditional fuels generally considered for metal cooled fast systems have been oxides and
metals. There has also been a long-term interest in carbides and nitrides.
Since fuels relevant to ADS (in their role as incinerators) will not contain large amounts of
fertile material, the (negative) Doppler temperature feedback would be small. This would
imply to maintain the subcriticality (1 K ) at a large, cost penalizing level. We should
remark, however, that critical systems using highly enriched uranium have been operated
extensively in the past. These systems had relatively low Doppler effect but were designed to
take advantage of other temperature feedbacks, such as thermal expansion (included outward
bowing) and/or moderator temperature coefficients.
Other isotopes other than U could be as well considered for designing systems with
enhanced Doppler, such as tungsten, hafnium or dysprosium, with resonance integrals 350,
2000 and 1500, respectively. With sufficient Doppler feedback, ADS systems could be safely
run at higher k 's.
Metal fuels have very good thermal properties and can be directly processed with
pyrochemistry. Experience with the integrated fast reactor (IFR) developed at the Argonne
National Laboratory demonstrated that burnups of 10 to 20 atom percent could be achieved
with these fuels.
Nitride fuels have good thermal properties and can be also used with pyrochemical
processing. Traditional nitride fuels are being studied for use in burning the minor actinides
while using the plutonium in fast or thermal reactors (double strata strategy) .
Molten salt fuels allow for the fuel to be dissolved in the coolant. This provides for a
homogenous mixture where fuel can be added and removed (quasi) continuously. This
continuos operation transforms the concern over the reactivity swing during burnup, to be
compensated by an appropriate (poison, or accelerator current) control, into that of correctly
adjusting the feed (fuel inlet) and bleed (fuel outlet) operations. Correct operation of a molten
salt reactor would sustain a constant amount of subcriticality, thereby avoiding burnable
absorbers, control rods, or changing the accelerator power. The traditional first barrier to
radionuclides release, the solid fuel form, is non-existent in molten salt fuels. However,
multiple barriers can be designed to compensate for this change in safety basis. Since molten
salt reactors process the fuel continuously, the quantity of fission products is reduced when
compare to a solid fuel design.
6 T. Mukaiyama, "Status of Partitioning &Transmutation R&D, and research needs for ATW from JAERI perspective", ATW
Meeting, USDOE/OCRWM Washington DC, 17-18 Feb. 1999. 7
Fuels based on the high temperature reactor (HTR) technology with coated particles could be
an option for operating at very high temperatures. There are basically two possible types of
particle fuel: sol-gel, developed by General Atomics, based on graphite kernels, coated with
silicon carbide, and the infiltrated kernel approach developed by BNL.
Sol-gel was developed in the HTGR program, and has been demonstrated for uranium and
plutonium carbides and oxides. Other actinides should perform well, in principle.
All particle fuel should be coated to enhance fission product retention, and protected against
reaction/erosion by the coolant. The choice of coating materials is based on compatibility with
the kernel and coolant, and the level of burn-up desired. In general, silicon-carbide or metal-
carbide are the materials of choice. A pyrolytic carbon intermediate layer is usually used
between the kernel and coating for fission product retention, and to protect the outer coating
for high burnups (over 700 GWd/t) with the sol-gel based particles.
The use of a bare particle geometry allows direct cooling of the particles. As a result, high
power densities, hence high flux levels can be achieved. This ensures high burnup rates for
the actinides and other fission products. The thermal margins in operating and accident
scenarios are also high.
The coated particle fuel considered above was developed in relation to thermal reactors. There
is also an interest to develop a similar fuel form for fast, or intermediate, systems (possibly,
with some ceramic outer layer, as TiN, and with particles of ~10-fold larger radius). Little
experience exists so far in this field and a fairly large R&D effort would be required.
Fission product burning 99 129
ADS incinerators are considered also for transmuting Tc and I by neutron absorption.
The design of the target material is under development but several issues can be addressed.
Tc plus a neutron becomes in the order of tens of seconds stable Ru which has similar
99 129 130
physical properties to Tc . However, I plus a neutron becomes Xe in the order of tens of
hours and Xe is a noble gas. In the case of Tc a target can be developed that will allow a
very long residence time. In the case of I pressure buildup is a concern which must be
accounted for in the target design and could limit the target life. Another difference between
the two fission products is their cross section. Tc has a thermal absorption cross section of
20 barns and a resonance integral of 300 barns. I has a thermal absorption cross section of
30 barns but a resonance integral of only 50 barns.
As previously mentioned, the use of Pb-Bi as coolant would help transmuting these fission
products, due to the larger number of scattering collisions, with respect to lighter coolants,
required by a neutron for escaping a capture resonance width.
In order to help the transmutation of Tc and I , some moderation of the flux is useful.
Unfortunately due to high thermal fission cross section of the MA, thermalization of the
neutrons can result in local power peaking problems. 8
Different ADS Concepts
In principle, any reactor design, reconfigured for source-driven subcritical operation, is a
viable option for consideration as the sub-critical blanket/burner for an ADS system.
In previous sections our main reference have been an IFR-like (Pb-Bi or Na cooled) system.
Below, we shortly describe two other concepts of interest as possible ADS candidates.
Molten Salt Systems
In the molten salt option, fuel and coolant are obviously the same medium. A reactor using a
molten salt mixture of uranium, thorium, beryllium and lithium fluorides has worked with
success for several years in Oak Ridge.
A major advantage of molten salts are the great flexibility for the insertion of MA and LLFP,
together with the capability of accommodating very high burn-ups. As molten salts, one can
envisage chlorides or fluorides. In the first case, operating temperatures are reasonably low
(600 to 700°C), but chlorides have some adverse properties, such as corrosion (particularly
with respect to steel) and a relatively high neutron absorption. In the second case, operating
temperatures would be higher, but fluorides seem more stable. In any case, use of molten salts
would need a very lengthy R&D effort, due to larger unknowns associated with material
selection, operation and general engineering approach to design, construction and licensing.
At JAERI a molten- salt fast ADS concept with chloride salt as target, fuel and coolant, and
with on-line processing, is studied as an alternative within their development program. The
material compatibility problem is the major concern. 7
In US a thermal molten salt ATW transmuter has been also analyzed . The system design
utilizes NaF-ZrF carrier salt. The advantages claimed for this design are:
1. No backend chemistry. Once the fuel is fluorinated it is maintained in the core until
2. Immediate denaturing of the plutonium once mixed with the molten salt of the core. This
would meet antiproliferation requirements.
3. Due to the homogenous nature of the fuel the reactivity change with burnup can be
minimized by continuous feed/bleed operations. A multiplication coefficient (K ) closer
to unity might then be adopted.
4. No need for fuel fabrication.
The disadvantages are:
1. Liquid fuel. This implies the reduction of one containment barrier (but there is no reason
to assume that equal safety cannot be achieved).
2. Corrosive fuel. Although this was a problem with the original molten salt reactor,
corrosion resistant materials have been developed for molten salt operation.
7 Annu. Rev. Nucl. Part. Sci., 48:505-556. 9
3. Mixing of fuel implies that 20% of the actinides remain at discharge. Another type of
reactors should be developed to further reduce the actinides.
4. Less favourable neutron economy with a thermal spectrum. The neutrons per fission are
about 7% less at thermal energies. The parasitic losses to fertile actinides are about a third
greater for thermal systems. This can be compensated by an appropriate accelerator power
and/or fuel enrichment increase.
High Temperature Gas Cooled Systems
High temperature gas-cooled systems use helium (or CO ) as coolant, whereas the fuel
elements contain coated particles embedded in a graphite matrix. In the German HTGR
(critical, modular) design , fuel spheres, each six centimeters in diameter, form a "pebble
bed", whereas prismatic blocks are favored in the USA (General Atomics ).
Reactivity control can be enhanced by adding burnable poisons or fertile material to the fuel
element. The addition of these materials would reduce the anticipated rapid drop in reactivity,
and lengthen the cycle time.
The particle form would offer a high-integrity final disposal option requiring no additional
processing. In this case, the particles would be encapsulated in a graphite matrix in a container
which can then be placed in a suitable repository.
The particle nature of the fuel offers the potential for on-line re-fueling, similar to that
employed in the German PBR, which provides additional flexibility for reactivity control. The
significant improvement of large gas turbine generators developed over the last decade is quite
reviving now the interest on these systems.
A variety of possible scenarios exist, depending on the type of cycle (open, or closed), fuel
type (solid, molten salt, coated particles), strategy, etc.
We may recall first the so called "double strata" option (closed cycle) consisting in:
a first layer comprehending LWR (and possibly) fast reactors, burning U and Pu,
− a second layer comprehending MA (and possibly Pu) ADS, and/or critical reactor burners.
For what concerns the first layer, the fissioning of plutonium in MOX form in LWR, as is
presently done with a single recycle strategy, and might in the future be incremented with
multirecycling, would reduce, if not eliminate, the use of fast reactors for Pu burning. The
8 W. Gröger, "Safety Aspects of New HTGR Designs in the Federal Republic of Germany", Int. Workshop on Safety of
Nuclear Installations of the Next Generation and Beyond, Aug. 28-31, 1989 Chicago.
9 M.P. La Bar and W.A. Simon, "The Modular Helium Reactor for the Twenty-First Century", The Uranium Institute
Twenty-Second Annual Symposium, 3–5 September 1997, London. 10
+1 anno fa
I contenuti di questa pagina costituiscono rielaborazioni personali del Publisher Atreyu di informazioni apprese con la frequenza delle lezioni di Ingegneria del nocciolo e studio autonomo di eventuali libri di riferimento in preparazione dell'esame finale o della tesi. Non devono intendersi come materiale ufficiale dell'università La Sapienza - Uniroma1 o del prof Gandini Augusto.
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