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Modulo di “Tecniche di vuoto e films
                         sottili”


 Study of hard coatings for
   steel protection from
Liquid Metal Embrittlement
Prof. Enzo Palmieri
Laurea in Scienza dei Materiali
Università di Padova
Liquid metal cooling

• Leno Facility LNL

• Liquid metal cooled reactors
   Nucleare IV generazione
   Nuclear Propulsion
• Spallation Target cooling for Accelerator
  Driven System for Nuclear Wast Trasmutations
EXTRAORDINARILY HIGH
        HEAT EXCHANGING POWER
• Fast neutron reactor cores tend to generate a lot
  of heat in a small space when compared to
  reactors of other classes.

• The liquid metals used typically have extremely
  good heat transfer characteristics

• Ideally the coolant should never boil as that
  would make it more likely to leak out of the
  system, resulting in a loss of coolant accident.
Part I


APPLICATION
Liquid Metal cooled nuclear Reactors


 An advanced type of fast neutron reactor
where the primary coolant is a liquid metal.

  Liquid metal cooled reactors were first
adapted for nuclear submarine use, but have
also been extensively studied for power
generation applications.
PROPULSION
Submarines
The Soviet Alfa class submarine used a reactor cooled by a
lead-bismuth alloy. USS Sea wolf (SSN-575) was the
second nuclear submarine, and the only U.S. submarine to
have a sodium-cooled nuclear power plant.
Leaks in its superheaters made the submarine's Sodium-
cooled reactor replaced with pressurized water reactors.

Nuclear aircraft
Liquid metal cooled reactors were studied for use in
nuclear aircraft as part of the Aircraft Nuclear Propulsion
program up to 1979. From a few years there is a renewed
interest in France, India, USA, Italy
LEAD-BISMUTH COOLED
 ACCELERATOR DRIVEN TRANSMUTATION SYSTEM

  The reference target design assumes to
have a hemispherical beam window made of
Chromium-molybdenum steel cooled by
flowing Pb-Bi
 One   of   the   high   priority
                                issues is
degradation of structural material in a
Pb-Bi coolant at high proton and neutron
fluxes and high temperatures
ADS PREREQUISITES
• In Japan, there is enough employment experience for liquid Pb-
Bi in period of about 17 years and absence of corrosion for the
thermal conductive materials (1Cr-0.5Mo steel) used under the
condition of natural convection with temperature around 400°C

• Extensive experience in the use as Russian submarines and in
R&D during about 50 years are available. As a result, it will be
able to lead approximately zero corrosion for Cr-Si materials by
adjusting oxygen film with oxygen concentration control between
10-7 to 10-5% mass
ADS PREREQUISITES
  Polonium forms PbPo in Pb-Bi, and the evaporation rate
become less three factor than that of Po, and
furthermore, the rate decreases in the atmosphere. The
effects of Po on employee and environment will not be
dominant in comparison with those of fission products

  In Bi-resource, a confirmed amount will be 260 000
tonnes and an estimated amount will become ten times of
the confirmed ones by including resources in Russia. This
shows there are enough amounts for ADS developments
Nuclear Spallation
  A particle accelerator shoots on a cooled Hg, Ta or
other heavy metal target to produce a beam of
neutrons with 20 to 30 neutrons expelled after each
impact

  European Spallation Source (ESS) should be in Lund,
Sweden and its construction is expected to be
completed around 2018–19

  Either a liquid Pb-Bi alloy, liquid mercury or solid
tungsten will be used in quantities of around 20 tonnes
IV Generation
Research into these reactor types was officially started by the Generation
IV International Forum (GIF) based on eight technology goals.
•  improve nuclear safety,
• improve proliferation
  resistance
• minimize waste and
  natural resource utilization
• decrease the cost to build
  and run such plants.
 The claimed benefits include:
 • Nuclear waste that lasts
   decades instead of millennia.
 • 100-300 times more energy
   yield from the same amount
   of nuclear fuel.
• The ability to consume existing nuclear waste for production of electricity
IV Generation
  The lead-cooled fast reactor features a fast-neutron-spectrum

liquid-metal-cooled reactor with a closed fuel cycle and a large

monolithic plant option at 1,200 MW.

  The fuel is metal or nitride-based containing fertile uranium and

transuranics. The LFR is cooled by natural convection with a reactor

outlet coolant temperature of 550 °C, possibly ranging up to

800 °C with advanced materials.
Part II


Liquid Metal Cooling
Liquid metal coolants

Coolant                 Melting point   Boiling point

Mercury                 -38.8°C         356.7°C

NaK                     -11Cº           785ºC

Sodium                  97.7°C          883°C

Lead-bismuth eutectic   123.5°C         1670°C

Lead                    327.5 °C        1749 °C
Cooling Criteria
  Water's boiling point is also much lower than most
metals demanding that the cooling system be kept at
high pressure to effectively cool the core.
  Pressurized water could theoretically be used for a fast
reactor, but it tends to slowdown neutrons and absorb
them.
  This limits the amount of water that can be allowed to
flow through the reactor core, and since fast reactors have a
high power density most designs instead use molten metals.
Mercury
   At LANL, Clementine was the code name for the world's
first fast neutron nuclear experimental scale reactor
   The maximum output was 25kW and was fueled by
Plutonium
 The core was cooled by liquid Mercury since
it is liquid at room temperature
  IT resulted that Hg was not an ideal cooling
medium due to its poor heat transfer characteristics,
high toxicity, high vapor pressure, low boiling point,
producing noxious fumes when heated, relatively low
thermal conductivity, high neutron cross section
Sodium and NaK
 Sodium and NaK don't corrode steel to any
significant degree and are compatible with many nuclear
fuels
 They do however ignite spontaneously on contact
with air and react violently with water, producing
hydrogen gas
 Neutron activation of sodium also causes these
liquids to become intensely radioactive during operation,
though the half-life is short
Lead
 The   advantage of a high boiling point,
compared to water, makes not needed the
pressurization of the reactor at high temperatures.
This   improves safety as it reduces the
probability of a dramatic loss of coolant accident,
and allows for safer designs
Lead
 Pb has     excellent neutron properties
(reflection, low absorption) and is a very potent
radiation shield against gamma rays. However,
because lead has a high melting point and a high
vapor pressure, it is tricky   to refuel and service
a lead cooled reactor.
Lead-Bismuth Eutectic
  The Lead melting point can be lowered for lead-bismuth eutectic
that is unfotunately                  highly corrosive                                   to most metals used
for structural materials.

  The eutectic alloy of lead (44.5%) and bismuth (55.5%) is a
proposed coolant for the lead-cooled fast reactor, part of the
Generation IV reactor initiative.

  It has a         melting point of 123.5°C                                                (pure lead melts at
327°C) and a boiling point of 1670°C.

  Alloys with between 30% and 75% bismuth all have melting points below 200°C.

  .
 While lead expands slightly on melting and bismuth contracts slightly on melting, LBE has negligible change in volume on melting.
LBE
                      an upper limit on the
 The corrosivity of Pb-Bi
velocity of coolant flow through the reactor due
to safety considerations.

  Furthermore, the higher melting points of Lead and
LBE may mean that solidification of the coolant
may be a greater problem when the reactor is operated
at lower temperatures.

                              Bi in LBE
 Finally, upon neutron radiation the
coolant will undergo neutron capture and
subsequent beta decay, forming polonium, a potent
alpha emitter.
Part III


Corrosion due to liquid metal flow
Liquid Metal Embrittlement
  For many systems in which a liquid metal is in
contact with a polycrystalline solid,

  deep liquid grooves form where the grain
boundary meets the solid-liquid interface.
Liquid Metal Cracking

   “A form of embrittlement that results from
the combined action of a tensile stress and a
liquid metal in contact with the alloy surface.
Metals with low melting temperatures, such as
mercury, cadmium and zinc, can cause liquid
metal cracking.”
   For example, liquid Ga quickly penetrates
deep into grain boundaries in Al, leading to
intergranular fracture under very small stresses.
The liquid metal may invade grain &
       interphase boundaries

    Hg + Al = Hg(Al)
                     PLAY MOVIE
    Hg(Al) + 6H2O = Al2O3.3H2O + H2 + Hg
Skikda Algeria – January 19, 2004




(Liquid Metal Embrittlement, LNG Plant, 27
     killed 72 injured, USD 30,000,000)
The report concluded that the escaped gas was from the
         cryogenic heat exchanger due to LME
Skikda Algeria – January 19, 2004




             Hg + Al = Hg(Al)
  Hg(Al) + 6H2O = Al2O3.3H2O + H2 + Hg
Brittle intergranular fracture
  Very deep grooves form at the intersections
of grain boundaries and at the surface of
systems where a liquid metal is in contact with a
polycrystalline solid.
  In some systems, such as Al-Ga, Zn-Ga, Cu-Bi
and Ni-Bi, the liquid film quickly penetrates
deep into the solid along the grain boundary
and leads to brittle intergranular fracture under
the influence of even modest stresses.
LME and Grain Boundaries: Al/Ga




                         Ludwig et al. (2006)
Microradiographs showing liquid Ga penetration
along an Al bicrystal grain boundary
Energies of GBs for simplified orientation space (a: symmetric tilt GB, b: symmetric twist
GB




          e.g. energy of symmetric tilt GB (Read and Shockley):

                             GB = B[A – ln()]
Schematic of GB with solute segregation




 Orientation space of GBs is 5-d (compared with surfaces that have 2-d orientation
 space). 5-d space often described by 3 Euler angles + vector perpendicular to GB plane.
Grain Boundaries (GBs)
Special type of interface in single phase materials. Play important role in properties of poly-
crystalline materials.
Anisotropy of Interfacial Properties
Interfacial Equilibrium
GB with surface




                          GB = (hkl)1 cos() + (hkl)2 cos()
 or for isotropic surface:   GB = 2s cos()
good wetting <90°                 bad wetting >90°           Grain boundaries


                                                                                   SL
                                                                   GB
                                                                                   /2
                                                                                   SL

                                                                  2 SP cos/2 =   GB



      LV                 V        (SV, LV, SL)                            S1L
               L                                          GB
SV                  SL
                                   mechanical equilibrium                  S2L
                          S        chemical equilibrium

                                                                   S1P + S2P = GB
            SV - SL     =   LV cos   (Young)
Example: AFM image of GB grooves at pure Cu surface
Example of GB wetting

Since GB is more anisotropic than SL, there can be conditions where some high
energy GBs are completely wet while low energy GBs are still dry.




 Wet GBs will lead to "liquid metal embrittlement"
Factors influencing corrosion

• Solution pH
• Oxidizing agent
• Temperature
• Velocity
• Stresses
• Impurity content
Stresses
Stresses
STRESSES
Velocity
• High velocity of corrosive medium increases
  corrosion.
• Corrosion pdts are formed rapidly, mainly because
  chemicals are brought to the surface at a high rate.
• The accumulation of insoluble film on the metallic
  surface is prevented. So corrosion resistance of
  these films decreases.
• The corrosion products s are easily stifled and
  carried away, thereby exposing the new surfaces
  for corrosion
The effect of impurities
   Polycrystalline Al
Many theories have been proposed for LME
•   The dissolution-diffusion model of Robertson and Glickman says that adsorption of the liquid
    metal on the solid metal induces dissolution and inward diffusion. Under stress these processes
    lead to crack nucleation and propagation.


•   The brittle fracture theory of Stoloff and Johnson, Westwood and Kamdar proposed that the
    adsorption of the liquid metal atoms at the crack tip weakens inter-atomic bonds and propagates
    the crack.


•   Gordon postulated a model based on diffusion-penetration of liquid metal atoms to nucleate
    cracks which under stress grow to cause failure.


•   The ductile failure model of Lynch and Popovich predicted that adsorption of the liquid metal
    leads to weakening of atomic bonds and nucleation of dislocations which move under stress, pile-
    up and work harden the solid. Also dissolution helps in the nucleation of voids which grow under
    stress and cause ductile failure.
However, …
a quantitative prediction
   of LME is still elusive
Galvanic corrosion
• It is associated with the flow of current to a
  less active metal from a more active metal in
  the same environment.
• Coupling of two metals, which are widely
 separated in the electrochemical series,
 generally produces an accelerated attack
 on the more active metal
Oxygen conc cell
• due to the presence of oxygen electrolytic cell

• i.e. diff in the amt of oxygen in solution at one
  point exists when compared to another
LME runs along Oxides fixtures




A perfectly and compact oxyde film is needed
Mercury readily “wets” most surfaces and
forms amalgams with a number of metals.


This is a potentially reactive metal protected
from attack by air and water by an oxide layer.

If the protective oxide layer is and liquid
mercury is present then an amalgam is formed
and this will allow rapid reaction with air or
water.
Hydrogen embrittlement
• hydrogen can penetrate carbon steel and react
  with carbon to form methane.
• The removal of carbon result in decreased strength.
• Corrosion is possible at high temp as significant
  hydrogen partial pressure is generated.
• This cause a loss of ductility, and failure by cracking
  of the steel.
• Resistance to this type of attack is improved by
  allowing with chromium / molybdenum.
Thin films, coatings, cladding are
mandatory for steel protection
DLC does not work mainly
 because of Graphite corrosion
• When carbon steel is heated for prolonged
  periods at temp greater than 455 C, carbon
  may segregated, which is then transformed in
  to graphite. So the structural strength of the
  steel is affected.
• Employing killed steels of Cr and Molybdenum
  or Cr and Ni can prevent this type of
  corrosion.
NITRIDING
Beneficial Effect of Nitriding:

•  Obtain high surface hardness
•  Increase wear resistance
•  Improve fatigue life
•  Improve corrosion resistance (except for stainless
  steels)
• Obtain a surface that is resistant to the softening
  effect of heat (at temperatures up to the nitriding
  temperature)
Legame Metallico         Legame Covalente            Legame Ionico

Boruri,                   Boruri,     Carburi     e Ossidi di
Carburi e Nitruri di      Nitruri di Al, Si, B;     Al, Zr, Ti, Be
Metalli di Transizione    Diamante


Es.: TiB2, TiC, TiN, WC   Es.: B4C, SiC, BN         Es.: Al2O3, ZrO2, BeO
Schema delle proprieta’ di Boruri (b), Carburi (c) e Nitruri (n)



                 Durezza   Fragilita’   Punto     Stabilita’   Coeff.Esp.   Aderenza    Tendenza
                                        fusione                termica      substrato   interagire

In basso grado
                 n         b            n         b            b            n           n


     i           c         c            b         c            c            c           c

In alto grado
                 b         n            c         n            n            b           b
Tipi di matching all’interfaccia Film/Substrato




        (a)                               (b)                      (c)


(a) Interfaccia fra sistemi coerenti fra materiali duri a legame metallico
(b) Interfaccia a fasi miste fra materiali duri metallici e materiali ionici
(c) Interfaccia a fasi non interagenti fra materiali a legame covalente
Proprietà di differenti materiali metallici duri

Fase   Densita'       Punto di     Durezza    Young     Resistiv.    Coeff. espans. termica
       (g/cm3)      fusione ( C)   (HV)      Modulo      (mW cm)             (10-6/K)
                                             kN/mm2

TiB2    4.50          3225          3000      560           7                7.8
TiC     4.93          3067          2800      470          52             8.0 - 8.6
TiN     5.40          2950          2100      590          25                9.4
ZrB2    6.11          3245          2300      540           6                5.9
ZrC     6.63          3445          2560      400          42             7.0 - 7.4
ZrN     7.32          2982          1600      510          21                7.2
VB2     5.05          2747          2150      510          13                7.6
VC      5.41          2648          2900      430          59                7.3
VN      6.11          2177          1560      460          85                9.2
NbB2    6.98          3036          2600      630          12                8.0
NbC     7.78          3613          1800      580          19                7.2
NbN     8.43          2204          1400      480          58                10.1
Fase    Densita'     Punto di     Durezza    Young   Resistiv.   Coeff. espans. termica
        (g/cm3)    fusione ( C)    (HV)     Modulo    (mW cm)            (10-6/K)
                                            kN/mm2


TaB2    12.58        3037         2100       680        14               8.2
TaC     14.48        3985         1550       560        15               7.1
CrB2     5.58        2188         2250       540        18               10.5
Cr3C2    6.68        1810         2150       400        75               11.7
CrN      6.12        1050         1100       400       640              (2.3)
Mo2B5    7.45        2140         2350       670        18               8.6
Mo2C     9.18        2517         1660       540        57            7.8 - 9.3
W2B5    13.03        2365         2700       770        19               7.8
WC      15.72        2776         2350       720        17            3.8 - 3.9
LaB6     4.73        2770         2530      (400)       15               6.4
Proprieta' di differenti materiali covalenti duri



Fase        Densita'  Punto di      Durezza   Modulo di Young   Resistiv.    Coeff. espans.
            (g/cm3) fusione( C)      (HV)        kN/mm2         (mW cm)     termica (10-6/K)
B4C          2.52      2450         3-4000         441          0.5e+6        4.5 (5.6)
BN cub.)     3.48      2730         ~ 5000         660          1e+18              -
C (diam.)    3.52      3800         ~ 8000         910          1e+20             1.0
B            2.34      2100         2700           490          1e+12             8.3
AlB12        2.58    2150 (dec)     2600           430          2e+12              -
SiC          3.22    2760 (dec)     2600           480           1e+5             5.3
SiB6         2.43      1900         2300           330           1e+7             5.4
Si3N4        3.19      1900         1720           210          1e+18             2.5
AlN          3.26    2250   (dec)   1230           350          1e+15             5.7
Proprieta' di differenti materiali eteropolari duri

Fase      Densita'    Punto fusione   Durezza    Modulo       Resistiv.    Coeff. espans.
          (g/cm3)         ( C)         (HV)       Young       (mW cm)     termica (10-6/K)
                                                 kN/mm2


Al2O3      3.98          2047          2100        400        1e+20             8.4
Al2TiO5    3.68          1894            -         13         1e+16             0.8

TiO2       4.25          1867          1100        205            -             9.0
ZrO2       5.76          2677          1200        190        1e+16          11 (7.6)
HfO2       10.2          2900          780          -             -             6.5
ThO2       10.2          3300          950         240        1e+16             9.3
BeO        3.03          2550          1500        390        1e+23             9.0
MgO        3.77          2827          750         320        1e+12            13.0
Il Ti-Al-N è alquanto simile al TiN. Ha la stessa struttura fcc, con la differenza che gli atomi di Al
sostituiscono quelli di Ti


Parametro reticolare   a: aTi-Al-N < aTiN in funzione del contenuto di Al




                       Cella unitaria del TiN con inclusioni di Alluminio

             Guardando il rapporto d’impacchettamento si capisce immediatamente
                    perché introduzione dell’ Al rende il materiale più duro
In sintesi, Cosa potrebbe funzionare?




Nitruri binari o ternari di Ti, Cr, Si

e ….. Ossidi?

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Lezione Metallo Liquido Corrosione

  • 1. Modulo di “Tecniche di vuoto e films sottili” Study of hard coatings for steel protection from Liquid Metal Embrittlement Prof. Enzo Palmieri Laurea in Scienza dei Materiali Università di Padova
  • 2. Liquid metal cooling • Leno Facility LNL • Liquid metal cooled reactors  Nucleare IV generazione  Nuclear Propulsion • Spallation Target cooling for Accelerator Driven System for Nuclear Wast Trasmutations
  • 3. EXTRAORDINARILY HIGH HEAT EXCHANGING POWER • Fast neutron reactor cores tend to generate a lot of heat in a small space when compared to reactors of other classes. • The liquid metals used typically have extremely good heat transfer characteristics • Ideally the coolant should never boil as that would make it more likely to leak out of the system, resulting in a loss of coolant accident.
  • 5. Liquid Metal cooled nuclear Reactors An advanced type of fast neutron reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for nuclear submarine use, but have also been extensively studied for power generation applications.
  • 6. PROPULSION Submarines The Soviet Alfa class submarine used a reactor cooled by a lead-bismuth alloy. USS Sea wolf (SSN-575) was the second nuclear submarine, and the only U.S. submarine to have a sodium-cooled nuclear power plant. Leaks in its superheaters made the submarine's Sodium- cooled reactor replaced with pressurized water reactors. Nuclear aircraft Liquid metal cooled reactors were studied for use in nuclear aircraft as part of the Aircraft Nuclear Propulsion program up to 1979. From a few years there is a renewed interest in France, India, USA, Italy
  • 7. LEAD-BISMUTH COOLED ACCELERATOR DRIVEN TRANSMUTATION SYSTEM The reference target design assumes to have a hemispherical beam window made of Chromium-molybdenum steel cooled by flowing Pb-Bi One of the high priority issues is degradation of structural material in a Pb-Bi coolant at high proton and neutron fluxes and high temperatures
  • 8. ADS PREREQUISITES • In Japan, there is enough employment experience for liquid Pb- Bi in period of about 17 years and absence of corrosion for the thermal conductive materials (1Cr-0.5Mo steel) used under the condition of natural convection with temperature around 400°C • Extensive experience in the use as Russian submarines and in R&D during about 50 years are available. As a result, it will be able to lead approximately zero corrosion for Cr-Si materials by adjusting oxygen film with oxygen concentration control between 10-7 to 10-5% mass
  • 9. ADS PREREQUISITES Polonium forms PbPo in Pb-Bi, and the evaporation rate become less three factor than that of Po, and furthermore, the rate decreases in the atmosphere. The effects of Po on employee and environment will not be dominant in comparison with those of fission products In Bi-resource, a confirmed amount will be 260 000 tonnes and an estimated amount will become ten times of the confirmed ones by including resources in Russia. This shows there are enough amounts for ADS developments
  • 10. Nuclear Spallation A particle accelerator shoots on a cooled Hg, Ta or other heavy metal target to produce a beam of neutrons with 20 to 30 neutrons expelled after each impact European Spallation Source (ESS) should be in Lund, Sweden and its construction is expected to be completed around 2018–19 Either a liquid Pb-Bi alloy, liquid mercury or solid tungsten will be used in quantities of around 20 tonnes
  • 11. IV Generation Research into these reactor types was officially started by the Generation IV International Forum (GIF) based on eight technology goals. • improve nuclear safety, • improve proliferation resistance • minimize waste and natural resource utilization • decrease the cost to build and run such plants. The claimed benefits include: • Nuclear waste that lasts decades instead of millennia. • 100-300 times more energy yield from the same amount of nuclear fuel. • The ability to consume existing nuclear waste for production of electricity
  • 12. IV Generation The lead-cooled fast reactor features a fast-neutron-spectrum liquid-metal-cooled reactor with a closed fuel cycle and a large monolithic plant option at 1,200 MW. The fuel is metal or nitride-based containing fertile uranium and transuranics. The LFR is cooled by natural convection with a reactor outlet coolant temperature of 550 °C, possibly ranging up to 800 °C with advanced materials.
  • 14. Liquid metal coolants Coolant Melting point Boiling point Mercury -38.8°C 356.7°C NaK -11Cº 785ºC Sodium 97.7°C 883°C Lead-bismuth eutectic 123.5°C 1670°C Lead 327.5 °C 1749 °C
  • 15. Cooling Criteria Water's boiling point is also much lower than most metals demanding that the cooling system be kept at high pressure to effectively cool the core. Pressurized water could theoretically be used for a fast reactor, but it tends to slowdown neutrons and absorb them. This limits the amount of water that can be allowed to flow through the reactor core, and since fast reactors have a high power density most designs instead use molten metals.
  • 16. Mercury At LANL, Clementine was the code name for the world's first fast neutron nuclear experimental scale reactor The maximum output was 25kW and was fueled by Plutonium The core was cooled by liquid Mercury since it is liquid at room temperature IT resulted that Hg was not an ideal cooling medium due to its poor heat transfer characteristics, high toxicity, high vapor pressure, low boiling point, producing noxious fumes when heated, relatively low thermal conductivity, high neutron cross section
  • 17. Sodium and NaK Sodium and NaK don't corrode steel to any significant degree and are compatible with many nuclear fuels They do however ignite spontaneously on contact with air and react violently with water, producing hydrogen gas Neutron activation of sodium also causes these liquids to become intensely radioactive during operation, though the half-life is short
  • 18. Lead The advantage of a high boiling point, compared to water, makes not needed the pressurization of the reactor at high temperatures. This improves safety as it reduces the probability of a dramatic loss of coolant accident, and allows for safer designs
  • 19. Lead Pb has excellent neutron properties (reflection, low absorption) and is a very potent radiation shield against gamma rays. However, because lead has a high melting point and a high vapor pressure, it is tricky to refuel and service a lead cooled reactor.
  • 20. Lead-Bismuth Eutectic The Lead melting point can be lowered for lead-bismuth eutectic that is unfotunately highly corrosive to most metals used for structural materials. The eutectic alloy of lead (44.5%) and bismuth (55.5%) is a proposed coolant for the lead-cooled fast reactor, part of the Generation IV reactor initiative. It has a melting point of 123.5°C (pure lead melts at 327°C) and a boiling point of 1670°C. Alloys with between 30% and 75% bismuth all have melting points below 200°C. . While lead expands slightly on melting and bismuth contracts slightly on melting, LBE has negligible change in volume on melting.
  • 21. LBE an upper limit on the The corrosivity of Pb-Bi velocity of coolant flow through the reactor due to safety considerations. Furthermore, the higher melting points of Lead and LBE may mean that solidification of the coolant may be a greater problem when the reactor is operated at lower temperatures. Bi in LBE Finally, upon neutron radiation the coolant will undergo neutron capture and subsequent beta decay, forming polonium, a potent alpha emitter.
  • 22. Part III Corrosion due to liquid metal flow
  • 23. Liquid Metal Embrittlement For many systems in which a liquid metal is in contact with a polycrystalline solid, deep liquid grooves form where the grain boundary meets the solid-liquid interface.
  • 24. Liquid Metal Cracking “A form of embrittlement that results from the combined action of a tensile stress and a liquid metal in contact with the alloy surface. Metals with low melting temperatures, such as mercury, cadmium and zinc, can cause liquid metal cracking.” For example, liquid Ga quickly penetrates deep into grain boundaries in Al, leading to intergranular fracture under very small stresses.
  • 25. The liquid metal may invade grain & interphase boundaries Hg + Al = Hg(Al) PLAY MOVIE Hg(Al) + 6H2O = Al2O3.3H2O + H2 + Hg
  • 26. Skikda Algeria – January 19, 2004 (Liquid Metal Embrittlement, LNG Plant, 27 killed 72 injured, USD 30,000,000) The report concluded that the escaped gas was from the cryogenic heat exchanger due to LME
  • 27. Skikda Algeria – January 19, 2004 Hg + Al = Hg(Al) Hg(Al) + 6H2O = Al2O3.3H2O + H2 + Hg
  • 28.
  • 29. Brittle intergranular fracture Very deep grooves form at the intersections of grain boundaries and at the surface of systems where a liquid metal is in contact with a polycrystalline solid. In some systems, such as Al-Ga, Zn-Ga, Cu-Bi and Ni-Bi, the liquid film quickly penetrates deep into the solid along the grain boundary and leads to brittle intergranular fracture under the influence of even modest stresses.
  • 30. LME and Grain Boundaries: Al/Ga Ludwig et al. (2006)
  • 31. Microradiographs showing liquid Ga penetration along an Al bicrystal grain boundary
  • 32. Energies of GBs for simplified orientation space (a: symmetric tilt GB, b: symmetric twist GB e.g. energy of symmetric tilt GB (Read and Shockley): GB = B[A – ln()]
  • 33. Schematic of GB with solute segregation Orientation space of GBs is 5-d (compared with surfaces that have 2-d orientation space). 5-d space often described by 3 Euler angles + vector perpendicular to GB plane.
  • 34. Grain Boundaries (GBs) Special type of interface in single phase materials. Play important role in properties of poly- crystalline materials.
  • 36.
  • 37.
  • 38. Interfacial Equilibrium GB with surface GB = (hkl)1 cos() + (hkl)2 cos() or for isotropic surface: GB = 2s cos()
  • 39. good wetting <90° bad wetting >90° Grain boundaries SL GB /2 SL 2 SP cos/2 = GB LV V (SV, LV, SL) S1L  L GB SV SL mechanical equilibrium S2L S chemical equilibrium S1P + S2P = GB SV - SL = LV cos (Young)
  • 40. Example: AFM image of GB grooves at pure Cu surface
  • 41. Example of GB wetting Since GB is more anisotropic than SL, there can be conditions where some high energy GBs are completely wet while low energy GBs are still dry. Wet GBs will lead to "liquid metal embrittlement"
  • 42. Factors influencing corrosion • Solution pH • Oxidizing agent • Temperature • Velocity • Stresses • Impurity content
  • 46. Velocity • High velocity of corrosive medium increases corrosion. • Corrosion pdts are formed rapidly, mainly because chemicals are brought to the surface at a high rate. • The accumulation of insoluble film on the metallic surface is prevented. So corrosion resistance of these films decreases. • The corrosion products s are easily stifled and carried away, thereby exposing the new surfaces for corrosion
  • 47. The effect of impurities Polycrystalline Al
  • 48. Many theories have been proposed for LME • The dissolution-diffusion model of Robertson and Glickman says that adsorption of the liquid metal on the solid metal induces dissolution and inward diffusion. Under stress these processes lead to crack nucleation and propagation. • The brittle fracture theory of Stoloff and Johnson, Westwood and Kamdar proposed that the adsorption of the liquid metal atoms at the crack tip weakens inter-atomic bonds and propagates the crack. • Gordon postulated a model based on diffusion-penetration of liquid metal atoms to nucleate cracks which under stress grow to cause failure. • The ductile failure model of Lynch and Popovich predicted that adsorption of the liquid metal leads to weakening of atomic bonds and nucleation of dislocations which move under stress, pile- up and work harden the solid. Also dissolution helps in the nucleation of voids which grow under stress and cause ductile failure.
  • 49. However, … a quantitative prediction of LME is still elusive
  • 50. Galvanic corrosion • It is associated with the flow of current to a less active metal from a more active metal in the same environment. • Coupling of two metals, which are widely separated in the electrochemical series, generally produces an accelerated attack on the more active metal
  • 51. Oxygen conc cell • due to the presence of oxygen electrolytic cell • i.e. diff in the amt of oxygen in solution at one point exists when compared to another
  • 52. LME runs along Oxides fixtures A perfectly and compact oxyde film is needed
  • 53. Mercury readily “wets” most surfaces and forms amalgams with a number of metals. This is a potentially reactive metal protected from attack by air and water by an oxide layer. If the protective oxide layer is and liquid mercury is present then an amalgam is formed and this will allow rapid reaction with air or water.
  • 54. Hydrogen embrittlement • hydrogen can penetrate carbon steel and react with carbon to form methane. • The removal of carbon result in decreased strength. • Corrosion is possible at high temp as significant hydrogen partial pressure is generated. • This cause a loss of ductility, and failure by cracking of the steel. • Resistance to this type of attack is improved by allowing with chromium / molybdenum.
  • 55.
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  • 57. Thin films, coatings, cladding are mandatory for steel protection
  • 58. DLC does not work mainly because of Graphite corrosion • When carbon steel is heated for prolonged periods at temp greater than 455 C, carbon may segregated, which is then transformed in to graphite. So the structural strength of the steel is affected. • Employing killed steels of Cr and Molybdenum or Cr and Ni can prevent this type of corrosion.
  • 59. NITRIDING Beneficial Effect of Nitriding: • Obtain high surface hardness • Increase wear resistance • Improve fatigue life • Improve corrosion resistance (except for stainless steels) • Obtain a surface that is resistant to the softening effect of heat (at temperatures up to the nitriding temperature)
  • 60. Legame Metallico Legame Covalente Legame Ionico Boruri, Boruri, Carburi e Ossidi di Carburi e Nitruri di Nitruri di Al, Si, B; Al, Zr, Ti, Be Metalli di Transizione Diamante Es.: TiB2, TiC, TiN, WC Es.: B4C, SiC, BN Es.: Al2O3, ZrO2, BeO
  • 61. Schema delle proprieta’ di Boruri (b), Carburi (c) e Nitruri (n) Durezza Fragilita’ Punto Stabilita’ Coeff.Esp. Aderenza Tendenza fusione termica substrato interagire In basso grado n b n b b n n i c c b c c c c In alto grado b n c n n b b
  • 62. Tipi di matching all’interfaccia Film/Substrato (a) (b) (c) (a) Interfaccia fra sistemi coerenti fra materiali duri a legame metallico (b) Interfaccia a fasi miste fra materiali duri metallici e materiali ionici (c) Interfaccia a fasi non interagenti fra materiali a legame covalente
  • 63. Proprietà di differenti materiali metallici duri Fase Densita' Punto di Durezza Young Resistiv. Coeff. espans. termica (g/cm3) fusione ( C) (HV) Modulo (mW cm) (10-6/K) kN/mm2 TiB2 4.50 3225 3000 560 7 7.8 TiC 4.93 3067 2800 470 52 8.0 - 8.6 TiN 5.40 2950 2100 590 25 9.4 ZrB2 6.11 3245 2300 540 6 5.9 ZrC 6.63 3445 2560 400 42 7.0 - 7.4 ZrN 7.32 2982 1600 510 21 7.2 VB2 5.05 2747 2150 510 13 7.6 VC 5.41 2648 2900 430 59 7.3 VN 6.11 2177 1560 460 85 9.2 NbB2 6.98 3036 2600 630 12 8.0 NbC 7.78 3613 1800 580 19 7.2 NbN 8.43 2204 1400 480 58 10.1
  • 64. Fase Densita' Punto di Durezza Young Resistiv. Coeff. espans. termica (g/cm3) fusione ( C) (HV) Modulo (mW cm) (10-6/K) kN/mm2 TaB2 12.58 3037 2100 680 14 8.2 TaC 14.48 3985 1550 560 15 7.1 CrB2 5.58 2188 2250 540 18 10.5 Cr3C2 6.68 1810 2150 400 75 11.7 CrN 6.12 1050 1100 400 640 (2.3) Mo2B5 7.45 2140 2350 670 18 8.6 Mo2C 9.18 2517 1660 540 57 7.8 - 9.3 W2B5 13.03 2365 2700 770 19 7.8 WC 15.72 2776 2350 720 17 3.8 - 3.9 LaB6 4.73 2770 2530 (400) 15 6.4
  • 65. Proprieta' di differenti materiali covalenti duri Fase Densita' Punto di Durezza Modulo di Young Resistiv. Coeff. espans. (g/cm3) fusione( C) (HV) kN/mm2 (mW cm) termica (10-6/K) B4C 2.52 2450 3-4000 441 0.5e+6 4.5 (5.6) BN cub.) 3.48 2730 ~ 5000 660 1e+18 - C (diam.) 3.52 3800 ~ 8000 910 1e+20 1.0 B 2.34 2100 2700 490 1e+12 8.3 AlB12 2.58 2150 (dec) 2600 430 2e+12 - SiC 3.22 2760 (dec) 2600 480 1e+5 5.3 SiB6 2.43 1900 2300 330 1e+7 5.4 Si3N4 3.19 1900 1720 210 1e+18 2.5 AlN 3.26 2250 (dec) 1230 350 1e+15 5.7
  • 66. Proprieta' di differenti materiali eteropolari duri Fase Densita' Punto fusione Durezza Modulo Resistiv. Coeff. espans. (g/cm3) ( C) (HV) Young (mW cm) termica (10-6/K) kN/mm2 Al2O3 3.98 2047 2100 400 1e+20 8.4 Al2TiO5 3.68 1894 - 13 1e+16 0.8 TiO2 4.25 1867 1100 205 - 9.0 ZrO2 5.76 2677 1200 190 1e+16 11 (7.6) HfO2 10.2 2900 780 - - 6.5 ThO2 10.2 3300 950 240 1e+16 9.3 BeO 3.03 2550 1500 390 1e+23 9.0 MgO 3.77 2827 750 320 1e+12 13.0
  • 67. Il Ti-Al-N è alquanto simile al TiN. Ha la stessa struttura fcc, con la differenza che gli atomi di Al sostituiscono quelli di Ti Parametro reticolare a: aTi-Al-N < aTiN in funzione del contenuto di Al Cella unitaria del TiN con inclusioni di Alluminio Guardando il rapporto d’impacchettamento si capisce immediatamente perché introduzione dell’ Al rende il materiale più duro
  • 68. In sintesi, Cosa potrebbe funzionare? Nitruri binari o ternari di Ti, Cr, Si e ….. Ossidi?