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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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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]


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


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


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


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


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


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


Results(Fuel Cycle Indicators)

VUJE, Inc., Okružná 5, 918 64 Trnava


2. Some PWR and VVER MOX Calculations by HELIOS

VUJE, Inc., Okružná 5, 918 64 Trnava


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


PWR Model in Fuel CyclesHELIOS 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


VV Fuel CyclesER-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


VV Fuel CyclesER-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


Profiled MOX Fuel Cycles

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


Concentration of Fuel CyclesPu in PWR Assembly

VUJE, Inc., Okružná 5, 918 64 Trnava


Development of Fuel CyclesPu

VUJE, Inc., Okružná 5, 918 64 Trnava


Final Results Fuel Cycles– PWRMOX Assembly

Weight Concentrations

VUJE, Inc., Okružná 5, 918 64 Trnava


, Weight Concentrations Fuel Cycles

Final Results – Average Values

VUJE, Inc., Okružná 5, 918 64 Trnava


Pin Power Distribution Fuel Cycles

PWR-900

MOX UOX

UOX UOX


Pu-239 Fuel Cycles(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


Conclusions ( Fuel Cycles2)

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


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

VUJE, Inc., Okružná 5, 918 64 Trnava


SUPERPHENIX and Fuel CyclesVVER-440

VUJE, Inc., Okružná 5, 918 64 Trnava


PSEUDO Fuel Assembly Fuel Cycles – 91 pins

PSEUDO Fertile Assembly – 91 pins

PSEUDO Assemblies in HELIOS 1.10

VUJE, Inc., Okružná 5, 918 64 Trnava


Reflector Fuel Cycles

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


Multirecycling of Fuel CyclesPu and MA in FR

VUJE, Inc., Okružná 5, 918 64 Trnava


Development of Fuel CyclesPu

VUJE, Inc., Okružná 5, 918 64 Trnava


Development of Fuel CyclesMA

Initial: 2.7 %MA in Fuel Part

VUJE, Inc., Okružná 5, 918 64 Trnava


Fuel Cycle Indicators Fuel Cycles

VUJE, Inc., Okružná 5, 918 64 Trnava


1. Fuel CyclesSpent 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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