technical meeting on strategies and opportunities for the
TRANSCRIPT
Fast reactor fuel cycle for two-component nuclear power
A. Shadrin, Yu. Mochalov, V. Skupov
Technical Meeting on Strategies and Opportunities for the Management of
Spent Fuel from Power Reactors in the Longer Timeframe
Bahadurgarh, India
25–29 November 2019
ОЭС
Востока
Nuclear power generation in Russia- 18,4% of the electricity
generated in the country (204.5 BILLION KWH)
northwest united energy
system
central
energy
system
united
energy
system of
Siberia
united energy system of
the Uralsunited
energy
system of
the south
united
energy
system of
the Middle
Volga
0,5%
united
energy
system of
the east
34%
42%
23% 30%4%
BIL
LIO
N K
WH
BIL
LIO
N K
WH
BIL
LIO
N K
WH
BIL
LIO
N K
WH
BIL
LIO
N K
WH
3
Russian Nuclear Power Plants: 35 nuclear power units, 29,1 GW
They produce 18,4% of the electricity generated in the country.
• VVER-1000/1200: 15 units (13 units VVER-1000 + 2 units VVER-1200) in
operation
• 6 units under construction (Baltic NPP -2 units, Kursk NPP -2 units,
Novovoronezh NPP-1, Leningrad NPP-1 unit )
•RBMK-1000: 10 units in operation (1-in the course of decommissioning )
•VVER-440: 5 units in operation till 2030, 3 units are in the course
of decommissioning
•EGP-6: 3 units in operation, 1- in decom.)
•BN-600 (FR) 1 units in operation
•BN-800(FR) 1 unit in operation
•FTNPP 1 unit - "Academician Lomonosov"
will replace Bilibino NPP (shout down in 2018-2021 years)
•Research reactors, Ice-breakers
•Submarines
Number of NPP power units in the portfolio of overseas projects - 33 POWER UNITS IN 12
COUNTRIES around the world
Nuclear power generation in Russia- 18,4% of the electricity generated in the
country (204.5 BILLION KWH)
Test Demonstration
Centre for SNF
reprocessing
(commissioning in
2021)
SNF
Centralized wet and dry
storage facilities
Underground research
laboratory
(commissioning in
2024 )
Reprocessing any type of
SNF
Modernization of the
HLW management
infrastructure MOX-fuel for BN-800 fabrication
Partitioning and
isotopes
production
SNFM infrastructure in Russia for closed NFC
4
SNF Reprocessing at PA Mayak
5
Routine reprocessing of WWER-440, BN-600, nuclear submarine, research and production reactor SNF, RBMK-1000 SNF unsuitable for storage, VVER-1000 SNF.
.
NIIP
NITI
IRM
Research reactor SNF shipment activities
Extraction Cascade of the EF-35 Extraction ( from 1996)
More than 1200 m3 of HLW
was processed with Cs-Sr recovering
cobalt dicarbollyde
Different types of HLW
Filtration
Extraction of 90
Sr and 137
Cs
Extract washing
Stripping of 90
Sr and 137
Cs
Regeneration of extractant
Recycle extractant
Raffinate after
recovery of Cs and Sr
Strip solution of 90
Sr
and 137
Cs
Further reprocessing
To vitrification
ChCoDiC
PEGOHO
Hn
polyethylene glycol
6
Permission for Underground Research Laboratory construction
is obtained
Preliminary stage of URL
construction is began
Krasnoyarsky Region,
Nizhnekansky massive
2018 – strategy of underground repository
construction
Картинка или карта
где много объектов
рядом
Underground
repository
Mining Chemical combine
7
Centralized dry RBMK &VVER-1000 SNF
storage facilitiesMOX-fuel for BN-800 fabrication
Centralized wet SNF
storage facilities
Test Demonstration Centre for SNF reprocessing
10
SNFM infrastructure in Mining &Chemical Combine
Замыкание ЯТЦ с использованием смешанного U-Puтоплива в РБН
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9
•U and Pu are involved in NFC and Np and Am will be involved•Cm will be stored for long time and could be involved in NFC•No limitation recycle of U and Pu
Main requirements for FR SNF reprocessing
technologies
Imperative
• Safety
• Ecological acceptance
• Economic efficiency
Technical
• Ability to reprocess SNF with low cooling
time and high burn-up
• Observance of Non-Proliferation Treaty
• Pu loss less than 0,1 %
• End products suitable for fuel fabrication
• Low volume of high-level waste
• Partitioning
Advantages
Independence from U sources;
No accidents requiring of population resettlement
No SNF accumulation
Improve of non-proliferation regime
Competitiveness as compared to other types of power
generations (excluding hydroelectric power plants)
Problems
Use of high radioactive materials
Necessarily of mental phobias overcome
Additional benefits
Utilization of Pu recovered from thermal reactors SNF;
Minor actinides ;
Recovery of high-priced SNF components
CNFC based on Fast Reactors
10
History of development of dense fuel in Russia
Years (fabrication -
irradiation)
Reactor Fuel Institution
Begin of 1970s –
2002
BR-10 UN IPPE (Obninsk)
Begin of 1980х –
2005
BOR-60 UN; UPuN RIAR (Dimitrovgrad)
State program
from 2011 and
”PRORYV” project
From 2013 – up to
now
BN-600;
BOR-60;
MIR; IBB-2M
UPuN Beloyarskaya NPP, RIAR, Institute of
Nuclear Materials, Bochvar Institute,
Siberian Chemical Combine,
SIA «Luch»
11
Main results of dense fuel research
Advantages of mixed nitride uranium-plutonium fuel (MNIT):
MNIT fuel operation temperature is significantly low an compare with melting point
Dense fuel is optimal for fast reactors from the safety and efficiency point of view.
An compare with oxide fuel: An compare with metal fuel:
High density Acceptable compatibility with shell
materials
higher thermal conductivity and
low store of accumulated energy
(advantage in emergency)
Lack of the hard temperature
restrictions
12
Tests of MNIT fuel into BN-600. Main results
Fabricated and put under irradiation 18 assemblers
(> 1000 pins containing MNIT fuel (shells of austenitic
and ferrite-martensitic steels).
Successfully completed tests of 10 assemblers (max
burn-up is 7.5% h. a.). 8 assemblers are still under
irradiations. 1 pin had gas leak.
Post irradiation tests are completed for 3 MNIT
assemblers with BN-600 pin dimensions and 4
assemblers with BN-1200 and BREST pin dimensions
The data necessary for fuel requirements,
fuel codes, and fuel pins design for
verification for BREST-OD-300 and BN-1200
first loading are obtained.
13
MNIT fuel fabrication technology
MNIT fuel fabrication/refabrication technology is developed and tested on 21
assemblers for BN-600 and 11 assemblers for BOR-60
The technological and design solutions were tested. these data are the basis for the
development of industrial technologies and design solutions for the MNIT fabrication
pfor BREST-OD-300 and BN-1200.
Since 2010, all stages from laboratory studies to industrial implementation have been
completed, including the development of equipment prototypes.
The unique automated experimental complexes allowing to produce nitride uranium-
plutonium fuel in the conditions of completely drained nitrogen inner-box atmosphere
are created
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MNIT fuel fabrication technology (2)
Technology and equipment were developed by cooperation of Bochvar Institute,
Sverdniikhimmash, Siberian Chemical Combine, "Sosny" and many others
In 2018, the technological lines were supplied to SCC site. The commissioning is
planned to perform in 2020
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PuO2
Mayk
MCC
PuO2
PuO2
SCC
Fuel fabrication)
Assemblers with (U,Pu)N
БРЕСТ-ОД-300
Carbothermic synthesis
Pellet fabrication
Fabrications
Pins / Am pins
Assemblers production
Reprocessing
Assemblers with (U,Pu,Np, Am)N of
assemblers with pins and Am pins (up
to 10 %)
Elemash
Ко
мпл
ект
ую
щие
твэл
ов
UO2
NCCP
Ком
пл
ект
ую
щие Т
ВС
(U, Pu)N
powder
Pellets
(U, Pu)N
Heterogeneous
granules
UO2 - Am2O3*
(U, Pu,Np, Am)N
powder
Pellets
(U, Pu,Np, Am)N
Pins Am pins
Homogenous
powder
(U, Pu,Np) O2 + UO2+Am2O3*
Pu
Fuel fabrication / refabrication on SCC site
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Specificity of FR SNF reprocessing
• High burn-up
(average 12 % h.a (>100 GVt*day/t)
instead of “comfortable” 45-55
GVt*day/t
• Low cooling time – “hot” SNF and
radwaste
(1 year instead of “comfortable” 4-7
years. FP are concentrated in radwaste
forms)
• High FP content
I, Ru, 14C, Mo, Zr, Tc are not a micro-,
there are a macro- components
• Specificity of fuel – high content of
Pu
Pu content (13-20%) leads to high
capacity of Pu affinage line and to strong
criticality control
17
PH-process is a combine technology for fast reactor SNF
reprocessing(should be tested in industrial scale)
1
8
PH-process:
• treat of SNF with low cooling time
and high content of fissile materials
(10-15 %)
• purification coefficient is about
~106
• satisfied to nonproliferation treaty
• loses of actinides are ≤ 0,1 %
• recovery and separation of Am
and CmHydrometallurgy part of PH-process is
suitable for MNIT and MOX with
2 years cooling time and burn-up
6-8 % heave metal
Minor actinides in fuel cycle
Experimental MNIT pellets contain MA are fabricated
The content of americium at the stages of the process was
determined by chemical method:- initial - Am – 0,594 %
- in powder - Am – 0,595 %
- in pellet - Am – 0,610 %
МРСА data for a sintered tablet :
Am – 0,5-0,6 %,
Average for 6:
center– 0,57 %
peripherals– 0,53 %
Gamma-spectrometry:
Am – 0,63-0,64 %
Np – 0,4 %
No Am in off-gases were determinated
the Am homogeneous transmutation is confirmed
Distribution of Am is homogeneous
19
20
HLW partitioning, MA recovery – main
results
Recovery and separation of Am and CmThe recovery of Am and Cm by TODGA from real Purex raffinate were tested at
"Mayak". Recovery of actinides > 99,9 % were achieved
Separation of Am and Cm by using a cation exchange resin
was successfully tested. This technology is effective, but
generates significant amounts of secondary radioactive
waste (used resin).
Set-up for high pressure liquid chromatography for separate
Am and Cm was tested with rare earth elements (Frumkin
and Bochvar Institutes). Use of HPLC could reduce volume
of secondary radioactive waste by more than 100 times.
Safety requirements for HPLC separation process are
determinated.
An experiment on the separation of Am and Cm is scheduled
for 2019.
Set-up for
Am and Cm HPLC
separation
20
SNFM industrial infrastructure today and tomorrow
• Thermal reactors SNF reprocessing (VVER-440, VVER-1000, RBMK-1000, AMB,
REMIX), fast reactors SNF MOX (with restrictions MNIT) BN-600, BN-800 and
transport and research reactors SNF
• Partitioning facility
• Industrial fabrication plant for BN-800 MOX fuel
• (Am bearing fuel can not be produced)
Exist:
RT-1
(Mayk)
MOX
fabrication
(MCC)
• 250-400 t/year, industrial reprocessing plant for LWR SNF (VVER-1000, REMIX),
• Partitionning is planned for testing in hot cells (1-5 tons of SNF per year)
• Posibility of reprocessing of FR SNF in mixture with LWR SNF (~1:10)
• MNIT (U-Pu-Np) 14 t/year (Rep U and RepPu can be used)
• Fabrication of Am containing fuel is possible
• MOX fuel fabrication is possible
Under
construction:
EDC (MCC)
MNIT
fabrication
(SCC)
• 10-25 tons/year reprocessing of fast reactor SNF (MNIT and MOX BREST-300, BN-
600, BN-800) with high burnup, low cooling time, average costs of reprocessing,
HLW partitioning are planed
• FR SNF reprocessing
• potential reprocessing of BN-1200, BR-1200 SNF, transport and research reactors
SNF
Planned for
the
construction:
Reprocessing
Fast Reactor
SNF
(SCC)
21
Possible main stages of closed nuclear fuel cycle
technologies development
Pu recycle Pu, Np recycle Pu, Np, Am recycle
Industrial recycle of
Pu, Np, Am and
partitioning
Partitioning
2020 20332025
22
SNF ReprocessingPA Mayak
SNF storage
Energy production - NPPs (LWR, FR)
Infrastructure of Advanced Fuel Cycles in Russia
23
U mining
U
FAs
SNF
SNF
SNF
FAs
FAs
HLW
HLW
FR/MSR
Am, Pu,
Cm, Np
SNF Reprocessing MCC
Fuel fabrication repU
Pu
MOX fuel fabrication U, Pu
REMIX fuel fabrication
Enrichment and U fuel fabrication
27
24
Conclusion
The results of the project ”Proryv", confirmed the technical and technological
feasibility of its basic principles and allow to begin a transition to a new
technological platform of nuclear power (closed nuclear fuel cycle) at 2030.
A prototype of the future nuclear power complexes is being to constructed at
the site of Siberian Chemical Combine
• Russia already operates nuclear system with thermal and fast neutron reactors and
developing the new innovative technologies and infrastructure for future sustainable
development with U-Pu multirecycling in thermal and fast reactors and reduction of
radiotoxicity of radwaste to be disposed
• In the area of SNF recycling Russia already operates reprocessing facility in Mayak
plant, has full scale recycling of repU and starts using Pu in fast rector fuel (BN-800)
• The new complex of NFC facilities with new technologies of reprocessing and
recycling as integrated plant is under creation in Krasnoyarsk area. There are
already exist a complex of SNF storage facilities , industrial plant for MOX-fuel
fabrication, and SNF reprocessing being deployed. An underground research
laboratory supporting the R&D program for RW deep geological disposal is also
being constructed there. These prospects also suggest REMIX-fuel fabrication.
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