development of physical conceptions of fast reactors · pdf filedevelopment of physical...

Development of physical

conceptions of fast reactors

YuS Khomyakov1) VI Matveev2) AV Moiseev2)

1)Institution ITC ldquoPRORYVrdquo Project Moscow Russia

2)State Scientific Center of the Russian Federation ndash Institute for Physics and Power Engineering Obninsk Russia

International Conference on Fast Reactors and Related Fuel Cycles Safe Technologies and Sustainable Scenarios (FR13) Paris France 4-7 March 2013

2

Main stages of fast reactor progress in Russia

1 Creation of fundamental basis of FRs (1950-1970)

critical zero-power BR-1

experimental reactors BR-510 BOR-60

2 Engineering and technical familiarization of Sodium

Fast Reactors (1970-1990)

first prototype of fast reactor BN-350

power fast reactor BN-600 of Beloyarsk NPP (up to 2020)

3 Discussions and conceptual investigations (1990-2010)

4 Current Russian Program (2010-2020)

commercialization SFR and development new type FR

power MOX ndashfuel reactor BN-800 with sodium coolant

commercial reactor BN-1200 with sodium coolant

prototype of LFR fast reactor BREST-OD-300 with Pb coolant

prototype of LVFR type reactor with Pb-Bi coolant

experimental fast reactor ndash MBIR with sodium coolant

3

Breeding idea and laquominimal T2 conceptraquo

BR-1 measured Breeding Ratio

BR = 25 plusmn 02

Basic points of laquominimal T2 conceptraquo

small critical mass high core power density

high breeding

short fuel cycle

Na ndash unique option of coolant

Development Na technology - main task

4

First power experimental fast reactor BR-510

BR-2 (1956-1957)

fuel ndash metallic Pu

power - 100 kW

coolant ndash Mercury (Hg)

BR-5 (1959-1964)

fuel ndash plutonium oxide

power - 5 MW

coolant ndash Sodium (Na)

BR-10 (1964-1998)

fuel ndash monocarbide and mononitride U

power - 10 MW


neutron flux up to 151015 cm-2s-1

BR-10 experience oxide and nitride fuel

5

First prototype fast reactor BN-350

The BN-350 reactor (1000 MW(th) 350 MW(e))

was the Worldrsquos first fast reactor-prototype the

loop-type reactor was cooled through 6

separate loops with sodium coolant

BN-350 confirm technical and engineering

reliability of fast reactors and gave first real

experience of operation

Problems with reliability of steam and gas

generators ndash the critical moment for BN program

Na coolant technology ndash the main problem of

fast reactors development

6

BN-600 reactor ldquoNa technology can be saferdquo

BN-600 has finally defined laquo classical imageraquo Russian BN

reactor

bull integral type of layout

bull three circulation loops (radioactive Na-Na heat

exchangers and nonradioactive Na-H2O steam generators)

bull oxide fuel (UO2 in BN-350 and in BN-600)

bull three zones of enrichment of core

bull availability of radial and axial blankets

Classical parameters of a core

bull power density ~ 450 kWm3 and ~ 48 kWm

bull burnup ~ 10-11 hm damage of cladding -80-90 dpa

bull output temperature of Na ~550С steel ~700С

bull operation time between fuel reloading ndash frac12 year

Basic trends of modern development of fast reactors

physical conceptions

safety achievement of core inherent safety

economy improvement of economical characteristics

U238 resources assimilation of closed nuclear fuel cycle

radioactive wastes transmutation of minor actinides

non-proliferation prevention of weapon-grade Pu

production and extraction of pure Pu

7

Key problems and ldquochoice forksrdquo

1 evaluation of feasibility of inherently safe fast reactors

2 choice of coolant sodium heavy liquid metal gas or steam

3 choice of fuel type МОХ carbide nitride or metal

4 expediency of use of fertile blankets

5 expediency and method (hetero- homo-geneous) of MA transmutation

6 fuel breeding level from BR~1 to BR~15

7 fuel breeding level in the core core with equilibrium fuel and BRcore ~1

8 power density in the core from ~500 MWm3 to ~250 MWm3 and lower

9 optimal fuel burn-up value from ~10 to ~15 and to ~20

10 fuel cycle duration from 1-3 years to 5 years and more

11 depth of fuel purification in reprocessing from 10-4 to 10-8

8

9

Breeding trend from BR-1 to BN-800

BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12

BN-800 BR ~ 10 divide 11

Factors

spectrum softening

oxide fuel (light element - O)

sodium coolant ( - Na)

priority of safety

Na plenum and

exclusion of upper blanket

thin radial blanket

Is the high breeding actual goal

Modern requirements to the closed fuel cycle

Minimal T2 is not highest priority

bull significant amount of Pu from VVER and

RBMK reactors

bull expected medium rate new nuclear

power

Fuel breeding

BR ~ 105 divide 12

Start-up loading (core power density)

mcritical ~ 6 t GW ( qv~ 200 MWm3 )

Duration of external fuel cycle

T le 3 years

10

Conception of ldquofast reactor start from U-235rdquo

11

Natural U

FP

Fast reactor

Isolation

Fission

Product

U Pu МА Enrichment U

20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year

ldquoTraditionalrdquo scenario

ldquoU-235 startrdquo scenario

Natural U

FP

Fast reactor

Isolation

Fission

Product

U Pu МА Enrichment U Thermal reactor U Pu МА

Main conceptual ways of reactor safety improvement

Minimization of excess reactivity for the fuel burn-up

Decrease of sodium void reactivity effect

Use of passive devices for reactivity control

Use of passive devices for decay heat removal

12

Conception of ldquozero excess reactivityrdquo

The concept sets as the purpose exception of

reactor runaway on prompt neutrons by limitation of

excess reactivity ρburn-uplt βeff

It means practical refusal of management of

campaign of fuel due to active systems of reactivity

control and

Transition to management due to internal

properties of a core and fuel

ldquoEquilibrium fuelrdquo is the fuel which is not changing

reactivity during burning out

Nitride fuel is preferable

Key issue is maintenance of sufficient accuracy of

forecasting of campaign (BN-600)

13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800

bull Case 1 (reference core) - Power

gradually decreases due to negative

Net reactivity core is heating up and

after 12 minute sodium boiling starts

in the core voiding of the upper core

part gives additional negative

contribution in Net reactivity and

power continues to go down

Reactor self-protection is provided

bull Case 2 (without Na plenum) and 3

(increased height of core) - sodium

boiling results in positive

contribution to Net reactivity reactor

runaway occurs leading to the core

disruption after 20-28 seconds

Reactor self-protection isrsquot provided

Conception of ldquozero sodium void reactivity effectrdquo

0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power

Relative primarysodium flow rate

0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect

Axial fuel expansion

SVRE

Net

Behavior of reactor parameters ULOF accident

Case 1

Case 2

Case 3

15

Reactivity effects Reactor power and

primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность

Расход 1 контур

0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность


Due to Doppler effect net

reactivity and power goes down

rapidly

Sodium boiling does not occurs

0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk

Self-protection features of cores with MOX and Nitride fuel

Comments

Power gradually decreases due

to negative Net reactivity core is

heating up and after frac12 minute

sodium boiling starts in the core

voiding of upper core part gives

additional negative contribution

in Net reactivity and power

continues to go down

Transmutation BN-350 experience and conclusions

16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233

42 Central plane of reactor Core height Core height

U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259

Effectiveness of МА transformation into fission

products in power reactors with low power density is

not high

Main reason - parasitic neutron capture

For example ~23 reactions leads to formation of

secondary actinides in BN-350

Secondary activity can exceed initial MA activity

In what sense of transmutation

Nuclides Burn-up of basic

isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22

Transmutation the general conceptual approach

17

MA transformation into the fuel isotopes

(similarly to the fuel breeding) - the main

method of their transmutation

Irradiation of short lived curium isotopes does

not make sense and therefore these should be

separated and stored till their decay to

plutonium

It is inexpedient to carry out MA

transmutation separately from the basic fuel

circulating in CNFC

Homogeneous transmutation along with fuel

is considered as the most effective approach

Although heterogeneous transmutation is not

excluded however it is effective if only MA

recycling is synchronized with the fuel recycling

242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor

BN-800 is first post-Soviet fast reactor in

Russia (start up at 2014)

o This project is aimed at the development of

the fuel cycle infrastructure and mastering

of the new types of fuel (MOX fuel)

o Sodium plenum making it possible to

assure zero void reactivity effect and

passive safety systems are special features

of BN-800 reactor design

Tests of these elements would lead to the

progress in the area of fast reactor safety

The problem of the proof of

economic efficiency before the

given project is not put

18

1 - vessel 2 -guard vessel 3 - core 4 - core diagrid

5 - core catcher 6 - silo 7 - main sodium pump

8 - upper stationary shielding 9 - large rotating plug

10 ndashcentral rotating plug 11 - protection cap

12 - refueling mechanism 13 - small rotating plug

14 ndash intermediate heat exchanger

BN-1200 fast reactor

Fuel cycle

bull fuel ndash mixed oxide or nitride

bull low power density in the core

bull external fuel cycle duration - 3 years

bull BR ndash 12 (oxide) -13 (nitride BRcore ~1)

bull MA utilization in the basic fuel

Safety

bull 2 types of passive control rods

bull flattened core sodium plenum

bull integration of all primary sodium systems in the

reactor vessel to eliminate radioactive sodium

leaks

Economical characteristics

bull optimization of layout approaches

bull increase of load factor by transition to one-year

refuelling interval

bull increase of the fuel burn-up

19

1 - intermediate heat exchanger 2 - reactor vessel

3 - guard vessel 4 - silo 5 - core diagrid

6 - core catcher 7 - reactor core 8 ndash pump nozzle

9 ndash main sodium pump 10 ndash cold trap

11 ndash control rod drives 12 ndash rotating plug

Demonstration BREST-OD-300 lead cooled reactor

bull coolant - lead

bull fuel ndash mixed nitride

bull low power density of the core

bull duration of external fuel cycle ndash 1-2 years

bull BR = BRcore ~ 105 without blankets

bull excess reactivity for the fuel burn-up leβeff

bull elimination of the most severe accidents by

means of natural properties specific for the

reactor its fuel coolant as well as reactor

design facilitating implementation of these

properties

bull rough cleaning of fuel from fission products and

curium

bull potential possibility of using enriched uranium

nitride as starting fuel with further transition to

mixed fuel is under investigation

20

1 ndash reactor vessel 2 ndash steam-water collectors


5 ndash channels of system emergency cooling

6 - main pump 7 ndash reactor core 8 ndash core diagrid

9 ndash steam generator

21 21

Conclusion (1)

Russian experience in developing fast reactors has proved clearly scientific

justification of conceptual physical principles and their technical feasibility

However the potential of fast reactors caused by their physical features has

not been fully realized

In order to assure the real possibility of transition to the nuclear power with

fast reactors by about 2030 it is necessary to consistently update fast reactor

designs for solving the following key problems

bull increasing of self-protection level of reactor core

bull improvement of technical and economical characteristics

bull solution of the problems related to the fuel supply of nuclear power and

assimilation of closed nuclear fuel cycle

bull disposal of long lived radioactive waste and transmutation of minor

actinides

22 22

Conclusion (2)

Russian program (2010-2020) on the development of basic concepts of the new

generation reactors implies successive solution of the above problems

New technical decisions will be demonstrated by development and assimilation

of the new reactors

BN-800 ndash development of the fuel cycle infrastructure and mastering of the

new types of fuel

BN-1200 reactor ndash demonstration economical efficiency of fast reactor and

new level of safety

BREST development and demonstration new heavy liquid metal coolant

technology and alternative design concept

2

Main stages of fast reactor progress in Russia

1 Creation of fundamental basis of FRs (1950-1970)

critical zero-power BR-1

experimental reactors BR-510 BOR-60

2 Engineering and technical familiarization of Sodium

Fast Reactors (1970-1990)

first prototype of fast reactor BN-350

power fast reactor BN-600 of Beloyarsk NPP (up to 2020)

3 Discussions and conceptual investigations (1990-2010)

4 Current Russian Program (2010-2020)

commercialization SFR and development new type FR

power MOX ndashfuel reactor BN-800 with sodium coolant

commercial reactor BN-1200 with sodium coolant

prototype of LFR fast reactor BREST-OD-300 with Pb coolant

prototype of LVFR type reactor with Pb-Bi coolant

experimental fast reactor ndash MBIR with sodium coolant

3



BR = 25 plusmn 02



high breeding

short fuel cycle



4


BR-2 (1956-1957)


power - 100 kW


BR-5 (1959-1964)


power - 5 MW


BR-10 (1964-1998)


power - 10 MW




5













6



reactor




















7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



3



BR = 25 plusmn 02



high breeding

short fuel cycle



4


BR-2 (1956-1957)


power - 100 kW


BR-5 (1959-1964)


power - 5 MW


BR-10 (1964-1998)


power - 10 MW




5













6



reactor




















7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



4


BR-2 (1956-1957)


power - 100 kW


BR-5 (1959-1964)


power - 5 MW


BR-10 (1964-1998)


power - 10 MW




5













6



reactor




















7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



5













6



reactor




















7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



6



reactor




















7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety











7













8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety















8

9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



9


BR-1 BR ~ 25

BR-2 BR ~16

BN-350 BR ~12


Factors

spectrum softening



priority of safety

Na plenum and


thin radial blanket





RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety






RBMK reactors


power

Fuel breeding

BR ~ 105 divide 12




T le 3 years

10


11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




11

Natural U

FP

Fast reactor

Isolation

Fission

Product


20

70

120

170

220

270

2010 2020 2030 2040 2050 2060 2070 2080 2090 2100

Pow

er

GG

W

year



Natural U

FP

Fast reactor

Isolation

Fission

Product







12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety








12







control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety









control and








13

-300

-250

-200

-150

-100

-050

000

050

0 100 200 300 td

d

kk

BN-1200-Nitr

BN-1200-MOX

BN-800


















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




















0 20 40 60 80 100Time s

00

02

04

06

08

10

Rel

u

nit

s

Power

Relative primary

sodium flow rate

0 5 10 15 20 25Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 10 20 30Time s

00

04

08

12

16

20

Rel

u

nit

s

Power


0 20 40 60 80 100Time s

-00025

-0002

-00015

-0001

-00005

0

00005

dk

k

0 5 10 15 20 25Time s

-00125

-001

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

0 10 20 30Time s

-00075

-0005

-00025

0

00025

0005

00075

001

00125

dk

k

Reactivity effects

Doppler effect


SVRE

Net


Case 1

Case 2

Case 3

15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



15


primary flow rate

0 100 200 300 400 500

Время с

00

02

04

06

08

10

Отн

ед

Мощность


0 100 200 300 400 500Время с

-00008

-00006

-00004

-00002

0

00002

dkk

MOX

Nitride

0 10 20 30 40 50 60 70 80 90 100

Время с

00

02

04

06

08

10

Отн

ед

Мощность




rapidly


0 10 20 30 40 50 60 70 80 90 100Время с

-0003

-0002

-0001

0

0001

dkk


Comments










16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




16

101

102

101

102

174

102

U-235 10

Cm(52)

Cm(43)

Am-241

Pu-240

U-233


U-235 (13)

15 Ir

Cell 243

244

226 225

242

260 259



not high







isotope

Accumulation of

secondary actinides

Actinides

burn-up

Am241 35 255 95

Np237 35 25 10

Cm244 44 33 10

Pu240 20 9 11

Pu238 34 12 22


17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




17







plutonium



circulating in CNFC






242Am 1602 ч

241Am 4322 г

241Pu 144 г

242Pu

376+5 л

242mAm 141 г

242Сm 1628 д

240Pu 6537 л

239Pu 24065 л

238Pu 8774 г

(nγ)

(nγ)

(1-ω)middot( nγ)

83 17

ИП

243Сm 285 г

244Сm 181 г

243Am 7380 л

244Am 101 ч

(n2n)

(nγ)

(nγ)

ω(nγ)

(nγ)

(nγ) (nγ)

BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



BN-800 fast reactor















18








Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




Fuel cycle






Safety





leaks




refuelling interval


19







bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety




bull coolant - lead










properties


curium




20






21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



21 21

Conclusion (1)













actinides

22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



22 22

Conclusion (2)




of the new reactors


new types of fuel


new level of safety



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