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

https://infc

is.iaea.o

rg/im

ages/N

FC

ISbackgro

und.g

if

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

14

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

15

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

16

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.

24

25

Partitioning allows

to reduce a cost

of radwaste isolation