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AER Meeting, Working Group F. Liblice, Czech Republic. April 6 – 9, 2010. THE HEAVY NUCLIDES TRANSMUTATION IN THE THERMAL AND FAST REACTORS CYCLES. Radoslav ZAJAC 1 -Petr DA RI LEK 1 -Vladim i r NE C AS 2. 1 VUJE, a.s. 2 Slovak University of Technology.

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slide1

AER Meeting, Working Group F

Liblice, Czech Republic

April 6 – 9, 2010

THE HEAVY NUCLIDES TRANSMUTATION IN THE THERMAL AND FAST REACTORS CYCLES

Radoslav ZAJAC1-Petr DARILEK1-Vladimir NECAS2

1VUJE, a.s.2Slovak University of Technology

1VUJE, a.s., Okruzna 5, Trnava, Slovakia, [email protected], [email protected]

2Slovak University of Technology, Faculty of Electrical Engineering and Information Technology, Ilkovicova 3, Bratislava, Slovakia,[email protected]

slide2

Presentation Parts

  • The Transmutation Fuel Cycles:
  • - Open Cycle (UOX)
  • - Mono- and Multi-Recycling Pu in VVER-440
  • - IMF Fuel Cycle
  • - ThOX Fuel Cycle
  • - Mono- and Multi-Recycling Pu in SUPERPHENIX
  • - Codes: TRITON in the System SCALE and HELIOS

2. Some PWR and VVER MOX Calculations by HELIOS

3. Transmutation of the VVER-440 Spent Fuel in the Fast Reactor

VUJE, Inc., Okružná 5, 918 64 Trnava

slide3

5 years

UOX

Storage

UOX

4.2% U-235

Spent Fuel

Fabrication

VVER-440

Enrichment

Final

Storage

Repozitory

U

45 years

Open Fuel Cycle (UOX)

VUJE, Inc., Okružná 5, 918 64 Trnava

slide4

Pu

2 years

5 years

UOX

Pu

Pu

4.2 % U235

UOX

S

VVER-440

Fabrication

T

REPROCESSING

8.5 % Pu

U

UOX

Irradiated

PUREX

U

O

MOX Fuel

MOX

R

Fabrication

VVER-440

100 % FP

MOX

0.1% U

A

0.1% Pu

100 % MA

G

Storage

Final

Depleted U

E

Repository

45 years

Mono- and Multi-Recycling Pu in VVER-440

VUJE, Inc., Okružná 5, 918 64 Trnava

slide5

2 years

Pu + MA

5 years

UOX

Pu + MA

Pu + MA

4.2 % U235

UOX

S

VVER-440

Fabrication

T

REPROCESSING

U, Zr

UOX

Irradiated

PUREX

U, Zr

O

Fabrication

UOX + IMF Fuel

R

UOX + IMF Fuel

VVER-440

100 % FP

0.1% U

A

0.1% Pu

0.1% MA

G

Final

UOX + IMF

Storage

E

Storage

45 years

IMF Fuel Cycle

VUJE, Inc., Okružná 5, 918 64 Trnava

slide6

2 years

Pu

5 years

UOX

Pu

Pu

UOX

4.2 % U235

S

Fabrication

VVER-440

T

REPROCESSING

Th, U

UOX

Irradiated

PUREX

Th, U

O

PuThOX Fuel

PuThOX

R

Fabrication

VVER-440

100 % FP

0.1% U

A

0.1% Pu

100 % MA

G

Final

Storage

PuThOX

Thorium

E

Repository

45 years

ThOX Fuel Cycle

VUJE, Inc., Okružná 5, 918 64 Trnava

slide7

2 years

Pu + MA

5 years

UOX

Pu + MA

Pu + MA

4.2 % U235

UOX

S

PWR-900

Fabrication

T

REPROCESSING

23.2 % Pu

U

UOX

Irradiated

2.7 % MA

PUREX

U

O

MOX

MOX FUEL

R

Fabrication

Fuel Part

100 % FP

0.1% U

A

MOX

0.1% Pu

SUPERPHENIX

0.1% MA

G

1450 MWe

Final

Depleted U

Storage

Fuel Part: 136 GWd/tHM

E

Storage

45 years

Mono- and Multi-Recycled Pu, MA in SUPERPHENIX

VUJE, Inc., Okružná 5, 918 64 Trnava

slide8

Results(Fuel Cycle Indicators)

VUJE, Inc., Okružná 5, 918 64 Trnava

slide9

2. Some PWR and VVER MOX Calculations by HELIOS

VUJE, Inc., Okružná 5, 918 64 Trnava

slide10

Based on OECD Depletion Calculation Benchmark devoted to MOX Fuel Cycles

Phase 1:Structure of 9 PWR Assemblies

- 8 UOX and 1 MOX Assembly

- Profiled MOX Assembly: high, medium and low

Phase 2:Structure of 7 VVER-1000 Assemblies

- 6 UOX and 1 MOX Assembly

- Profiled MOX Assembly: high, medium and low

Phase 3:Structure of 7 VVER-440 Assemblies

- 6 UOX and 1 MOX Assembly

- Profiled MOX Assembly: high, medium and low

Phase 4 - 6:PWR,VVER-1000 & VVER-440 Assembly in InfiniteLattice

Models of Structures in HELIOS 1.9

VUJE, Inc., Okružná 5, 918 64 Trnava

slide11

PWR Model in HELIOS 1.9

Average Content of

Pu/(U+Pu+Am):4.42%

Burnup of UOX Assembly:

24 GWd/tHM + 34 GWd/tHM

Burnup of MOX Assembly:

app. 42 GWd/tHM

Profiled MOX Assembly:

Reds – HIGH (5.516 % Pu);

Blues –MEDIUM (4.33 % Pu);

Pinks –LOW (2.856 % Pu);

VUJE, Inc., Okružná 5, 918 64 Trnava

slide12

VVER-1000 Model

Average Content of

Pu/(U+Pu+Am):4.42%

Burnup of UOX Assembly:

24 GWd/tHM + 31 GWd/tHM

Burnup of MOX Assembly:

app. 42 GWd/tHM

Profiled MOX Assembly:

Reds – HIGH (5.516 % Pu);

Blues –MEDIUM (4.33 % Pu);

Pinks –LOW (2.856 % Pu);

VUJE, Inc., Okružná 5, 918 64 Trnava

slide13

VVER-440 Model

Average Content of

Pu/(U+Pu+Am):4.42%

Geometry: Gd-2 Assembly

Burnup of UOX Assembly:

24 GWd/tHM + 35 GWd/tHM

Burnup of MOX Assembly:

app. 42 GWd/tHM

Profiled MOX Assembly:

Reds – HIGH (5.516 % Pu);

Blues –MEDIUM (4.33 % Pu);

Pinks –LOW (2.856 % Pu);

VUJE, Inc., Okružná 5, 918 64 Trnava

slide14

Profiled MOX

Assembly:

Red – (5.516 % Pu);

Blue –(4.33 % Pu);

Pink –(2.856 % Pu);

LWR Models in Infinite Lattice

Average Content of

Pu/(U+Pu+Am):4.42%

Burnup of MOX Assembly:42 GWd/tHM

VUJE, Inc., Okružná 5, 918 64 Trnava

slide15

Concentration of Pu in PWR Assembly

VUJE, Inc., Okružná 5, 918 64 Trnava

slide16

Development of Pu

VUJE, Inc., Okružná 5, 918 64 Trnava

slide17

Final Results – PWRMOX Assembly

Weight Concentrations

VUJE, Inc., Okružná 5, 918 64 Trnava

slide18

, Weight Concentrations

Final Results – Average Values

VUJE, Inc., Okružná 5, 918 64 Trnava

slide19

Pin Power Distribution

PWR-900

MOX UOX

UOX UOX

slide20

Pu-239(PWR):

- 63.3 %

Pu-239(VVER-1000):

- 62.0 %

Pu-239(VVER-440):

- 54.3 %

Pu(PWR):

- 33.0 %

Pu (VVER-1000):

- 32.6 %

Pu (VVER-440):

- 26.5 %

Conclusions (1)

  • Average Pu Content for PWR, VVER-1000 and 440 Assemblies: 4.42 %,Final Burnup: 42 GWd/tHM
  • Reduction of Pu,MOX Assembly as a Super Cell Part:
  • Actinides:

[Np+Am+Cm+Bk+Cf](PWR):

0.21 %

[Np+Am+Cm+Bk+Cf](VVER-1000):

0.21 %

[Np+Am+Cm+Bk+Cf](VVER-440):

0.22 %

VUJE, Inc., Okružná 5, 918 64 Trnava

slide21

Conclusions (2)

1. Spent LWR UOX Assembly:app. 1 % Pu

2. Reprocesing of 4.5 LWR UOX Spent Assemblies

1 MOX Assembly: 4.42 % Pu

3. Hypothesis:If is Possible to Spent 60 % of Pu-239in MOX

PuDepletionLeads to Pu-239 Spending from

2.7 LWR UOX Spent Assemblies

VUJE, Inc., Okružná 5, 918 64 Trnava

slide22

3. Transmutation of the VVER-440 Spent Fuel in the Fast Reactor

VUJE, Inc., Okružná 5, 918 64 Trnava

slide23

SUPERPHENIX and VVER-440

VUJE, Inc., Okružná 5, 918 64 Trnava

slide24

PSEUDO Fuel Assembly – 91 pins

PSEUDO Fertile Assembly – 91 pins

PSEUDO Assemblies in HELIOS 1.10

VUJE, Inc., Okružná 5, 918 64 Trnava

slide25

Reflector

1/6 Core of SUPERPHENIX;

Colour part:Subject of Calculation

Blanket

Blanket: fertile assembly,

depleted U

Fuel part

Fuel part: pseudo assembly, MOX 23.2 % Pu, 0.25 % U-235

Calculation Area

VUJE, Inc., Okružná 5, 918 64 Trnava

slide26

Multirecycling of Pu and MA in FR

VUJE, Inc., Okružná 5, 918 64 Trnava

slide27

Development of Pu

VUJE, Inc., Okružná 5, 918 64 Trnava

slide28

Development of MA

Initial: 2.7 %MA in Fuel Part

VUJE, Inc., Okružná 5, 918 64 Trnava

slide29

Fuel Cycle Indicators

VUJE, Inc., Okružná 5, 918 64 Trnava

slide30

1. Spent VVER-440 UOX Assembly:app. 1 % Pu

2. Reprocesing of 20.05VVER-440 UOX Assemblies

1 MOX SUPERPHENIX Assembly: 23.2 % Pu

3. Mass of Fuel to the repository:

Sum of repr. losses [kg/TWhe]: 2.09E+001.81E-01

SUPERPHENIX

Sum of FPs [kg/TWhe]: 1.01E+029.48E+01

VVER-440

Equilibrium(Fuel part)

Total of loss.+FPs [kg/TWhe]: 1.03E+029.66E+01

Pu [kg/TWhe]: 3.15E+011.79E+02

Separated U [t/TWhe]: 2.06E+000.66E-01

Conclusion

VUJE, Inc., Okružná 5, 918 64 Trnava

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