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Verifying non-diversion of
nuclear material from
naval fuel cycles under
the Nonproliferati
on Treaty(general)
1. Security risks (nuclear terrorism and proliferation)associated with the use of HEU for naval reactor fuel by
the US/UK, Russia, India and perhaps other countries in the future
2. The potential obstacle to nuclear disarmamentthat large reserves of HEU for naval reactor fuel could
pose for deep cuts and ultimately nuclear disarmament.
3. Verifying non-diversion of nuclear material from naval fuel cycles under the Nonproliferation Treaty
and a future Fissile Material Cutoff Treaty
MY PRESENTATION FOCUS
The Issues(according Prof von Hippel
presentation)
Sumarine Fuel: LEU x HEU• Certain design tradeoffs exist between
the use of highly-enriched uranium (HEU) versus the use of low enriched uranium (LEU) as a nuclear submarine reactor fuel with regard to such factors as:
core lifecore size
total powerreactor safetyLANNING, D.D.; IPPOLITO,T. Some Technical Aspects of the Use of Low-Enriched vs. High-Enriched
Uranium Fuel in Submarine Reactors, in Conference on the Implications of Acquisition of Nuclear Powered Submarines by Non-Nuclear Weapons States Proceedings, MIT, Cambridge, USA, 1989.
Submarine Fuel: LEU x HEU• The fuel for the first nuclear submarine Nautilus
and her prototype STR was metallic alloyed HEU – in principle a low U density fuel (early 50´s)
• Which drivers did push Rickover to this decision? Considering the state-of-art at these times, the trade-offs were not the same Availability of HEU Technological process to obtain U metal already developed Less U content in the alloy, less radiation damage to the fuel –
a problem for early graphite-gas reactors U metal fuelled Early development of a suitable metal to be alloyed –
Zirconium Time constraint of the project Non proliferation did not still enter in the dictionaries
Submarine Fuel: LEU x HEU• Why USA did not change its option, considering the
evolution of the state-of -the-art of nuclear fuel, with new solutions more dense in atomic U, as UO2 and many others?
Good results for this option in terms of the current trade-off: High core life, low core size, high total power, no safety
problems
R&D effort in the original option, still better results Industrial effect: an infrastructure was established Availability of HEU Non proliferation entered in the dictionaries but not in
the US Navy´s ones
Submarine Fuel: LEU x HEU• Why did France choose HEU in early 60
´s?
Few HEU available: total priority for weapons
Brand new “Force de Frappe”, low enrichment capacity
HEU for 1st criticality of PAT (land prototype) supplied by USA
But nothing more after, neither ToT (transfer of technology)
I guess …
First SSBN class using HEU
form and source of supply unknown
Submarine Fuel: LEU x HEU• Why did France change to LEU in early
70´s?
Higher density UO2 rod fuel already developed for PWRs
Rod fuel weakness for submarine use: new UO2 solution
UO2 “caramel” plate fuel developed for first SSN class
Not so good results terms of the current trade-off:
But the use of an integral design rather than a loop-type design could compensate for the larger core size.
Submarine Fuel: LEU x HEU• Why France did not keep HEU?
HEU availability remains limited, large LEU availability George Besse I in operation: final enrichment at Pierrelatte No success in centrifuge development
R&D effort in the LEU option, still better results Mainly in terms of integral PWR design compensating core
size Core life not as important as in USA (French Navy is not “7
oceans”) No safety problems for this option
Industrial effect: an infrastructure was established Non proliferation entered in the dictionaries but not in
the Marine Nationale´s ones
Submarine Fuel: LEU x HEU• Why did Brazil choose LEU in early 80´s?
Prudent to start with a proven technology (UO2 fuel rods) with a lot of information and experimental data in open sources for the land prototype (nowadays called LABGENE) No expertise in dealing with metallic uranium and practically no
information and experimental data available in open sources
Non proliferation entered in all Brazilian dictionaries: dealing with metal HEU was not a good political approach nor a sound technical one
But UO2 rods is not a good technical solution for submarines (but it was adopted successfully for Otto Hahn German merchant ship)
Submarine Fuel: LEU x HEU• Why did Brazil choose LEU in early 80´s?
So, a better fuel for the real nuclear submarine reactor core must be developed.
Which options keeping UO2 and LEU? “Caramel” plate fuel, at these times already a proven solution Dispersion fuels CERMET and CERCER, the first one looking better
R&D programs launched to explore both alternatives Good results for both, including irradiation of mini-plates in
Brazilian research reactor IEA-R1 for “caramel”
Decision will be make in the future on first submarine core Rods? Caramel Plates? Dispersion CERMET plates? It depends on real time schedule
Submarine Fuel: LEU x HEU• Will Brazil change to HEU in late 2020
´s?
Hard to find a rationale for thatThe reasons for France not keeping HEU are all
applicable to Brazil not changing to HEU
with one more strong motivation:
Non proliferation is an integral part ofBrazilian Navy dictionary
Verifying non-diversion of
nuclear material from naval fuel
cycles under the Nonproliferation
Treaty
(Brazil and Argentina)
Assuring non-diversion of LEU produced for
brazilian naval propulsion reactors(adapted from Prof von Hippel presentation)
Boxes outlined in red could be dealt with by standard IAEA approaches forland-based reactors. Others Brazilian Navy will cooperate to establish a sounder approach
Monitored LEU stockpile inunclassified form
Fabricated fuelLEU mass balanceContainer sealed
Spent fuel storage insealed container
Mass balance for LEU?
Proliferation risks
Diversion of UF6 or UO2 in powder production facility
Countermeasure: dealt with by standard IAEA approaches for land-based reactors (last LEU mass balance)
Diversion of UO2 in fuel rod/plate fabrication facility
Countermeasure: standard approaches do not apply
Special procedures (INFCIRC/435) must give reasonable assurance UO2 go out of the facility only in the form of a sealed container with a number of fuel elements
No new mass balance (protecting final fuel form)
Diversion of fuel elements from fresh fuel container
Only a risk if exists an undeclared dedicated facility to “reprocess” fresh fuel: very very low risk
Countermeasure: fresh fuel container goes direct to a monitored interim storage near refueling facilities, keeping the balance of mass in terms of number of containers in and out this facility.
Proliferation risks
Diversion of fuel elements during refueling Only a risk if exists a dedicated facility to “reprocess”
fresh fuel: very low risk
Countermeasure: standard approaches do not apply
Special procedures (INFCIRC/435) must give reasonable assurance there is no route to divert a fresh fuel element
Mass balance in terms of sealed container in, unsealed container (empty) out
After completing works, refueling hatch sealed in a checkable way
Proliferation risks
Diversion of fuel elements during reactor operation
Only a risk if exists undeclared dedicated facilities for defueling and further reprocessing irradiated fuel: very very low risk
Countermeasure: Special procedures (INFCIRC/435) must give reasonable assurance there is no diversion checking refueling hatch seals after a operational cycle to be defined
Proliferation risks
Diversion of fuel elements during reactor defueling
Operation done in declared facilities
Only a risk if exists undeclared dedicated facilities for reprocessing irradiated fuel : very very low risk
unloaded irradiated fuel elements go to a cooling pool without inspection (protecting final fuel form)
Countermeasure: Special procedures (INFCIRC/435) must give reasonable assurance there is no route to divert an irradiated fuel element from cooling pool
Proliferation risks
Diversion of fuel elements off cooling pool This operation will be done in very long term (around 10
years after defueling) and, consequently, in a very different context
But it will be done to an interim or final disposal facility, as there is no plans in Brazil to build a reprocessing facility
Countermeasure: dealt with by standard IAEA approaches for land-based reactors as at this time, the current fuel design will be very different from the older ones
The same if Brazil would develop a reprocessing facility in the long term
Proliferation risks
Over and above this paradox, Brazil is making an irreprehensible “homework” in non proliferation issues
Vert
ical
Vert
ical
HorizontalHorizontal
"We must abandon the unworkable
notion that it is morally reprehensible for
some countries to pursue weapons of
mass destruction, yet morally
acceptable for others to rely on them for
security - and indeed to continue to
refine their capacities and postulate
plans for their use."
(Mohamed ElBaradei)
NON PROLIFERATION IN NON PROLIFERATION IN BRAZILBRAZIL
UNIQUE SUCCESS EXPERIENCE UNIQUE SUCCESS EXPERIENCE
NON PROLIFERATION IN NON PROLIFERATION IN BRAZILBRAZIL
UNIQUE SUCCESS EXPERIENCE UNIQUE SUCCESS EXPERIENCE• Brazilian Constitution Brazilian Constitution proscribe all non-pacific uses proscribe all non-pacific uses of nuclear energyof nuclear energy– Member of NPTMember of NPT
– Member of Tlatelolco TreatyMember of Tlatelolco Treaty
} A remarkableA remarkablerecord of more record of more than 25 than 25 years without years without
technical technical deviations or deviations or
suspicious suspicious eventsevents
• All nuclear installations fully safeguarded– Multilateral agreements (1990 +
1994) (Brazil – Argentina – ABACC) + IAEA
• ABACC – bilateral regional agency
– IAEA full escope (NPT - 1997)
As Japan, Germany and Netherlands, has 2+1 enrichment plants fully safeguarded
Brazilian centrifuge program was never suspected being “proliferant” neither part of any international “black-marketing”
Has produced 20% batches for research reactor fuel under full scope safeguardsLEI
USIDE
RESENDEEnrichmentfacility
NON PROLIFERATION IN NON PROLIFERATION IN BRAZILBRAZIL
UNIQUE SUCCESS EXPERIENCE UNIQUE SUCCESS EXPERIENCE