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Molten salt reactor: Overview and perspectives

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Victor Ignatiev, Olga Feyenberg Kurchatov Institute Recent molten salt reactor (MSR) developments in Europe and Russia addressan advanced large power unit without graphite in the core. In new MSR concepts neutron spectrum is hard enough and the reprocessing rate strongly reduced compared to prior graphite moderated Th-U MSBR design developed at United StatesORNL. The consideration done demonstratesthe MSR potential as the system with flexible fuel cycle options which can operate with different loadings and make up scenarios based on transuranic elements from spent LWR fuel without and with Th-U support. This system may operate in the actinide recycler and transmuter, convertor as well as breeder modes without essential changes in the core/blanket configuration
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MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 1 Molten salt reactor: Overview and perspectives Abstract
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Page 1: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 1

Molten salt reactor: Overview and perspectives

Abstract

Page 2: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

2 ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012

Introduction

Page 3: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 3

Table 1: The basic characteristics of molten salt systems

Design MSBR [2,3] MSFR [6 ] MOSART [5,7]

Type Breeder Breeder Burner/converter

Neutron spectrum Thermal Fast Fast

Number of fluid streams 2 1 2 2 1 2

Thermal capacity, MW 2 250 2 250 3 000 3 000 2 400 2 400

Fuel salt temperature, C 566/704 566/704 600/750 700/850 600/720 600/720

Fuel salt composition, mole %

68LiF 31BeF2 0.2UF4

72LiF 16BeF2

12ThF4

0.2UF4

77.5LiF 20ThF4 2.5UF4

78LiF 16ThF4

6.5TRUF3

72LiF 27BeF2 1TRUF3

72LiF 27BeF2 1TRUF3

Blanket salt composition, mole %

71LiF 2BeF2 27ThF4

No 78LiF 22ThF4

78LiF 22ThF4

No 75LiF 5BeF2 20ThF4

Fuel cycle U -Th U -Th U-Th TRU-Th-U w/o U,Th TRU-Th-U

Soluble fission product removal time, EFPD

30-50 10-30 418 418 300 300

Transmuter mode

Page 4: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

4 ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012

Figure 1: Ring core configuration

Figure 2: Concentrations for actinide and lanthanides trifluorides in fuel salt vs. time for ring core

Solid line – 233

U to stock, dashed line – 233

U recycling from blanket to fuel stream

Thorium blanket

Fuel salt

Page 5: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 5

Figure 3: Equilibrium TRUF3 concentration in fuel salt (in mole%) vs. time for ring core configuration

Solid line – 233

U to stock, dashed line – 233

U recycling from blanket to fuel stream

Page 6: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

6 ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012

Figure 4: TRU loading and 233

U production for two-fluid ring core configuration

Figure 5: Critical TRUF3 concentration required for transition to different feed loadings vs. Pu/(Np+MA) ratio in it

Figure 6: Concentrations of TRU and lanthanides trifluorides vs. time for ring core with fuel make up transition from Pu/(Np+MA) = 9 down to Pu/(Np+MA) = 2 after 10 years of operation

0.0%

0.2%

0.4%

0.6%

0.8%

1.0%

1.2%

1.4%

0 10 20 30 40 50 60

t, eff. years

Co

ncen

trati

on

, m

ol. %

Soluble FP

TRU [Pu/(Np+MA):9/1]

TRU [Pu/(Np+MA):2/1]

TRUF3 solubility in fuel salt at 600C

Page 7: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 7

Breeder mode

Table 2: Critical TRUF3 concentration in the fuel salt

Salt solvent system, mole % Fuel addition, mole %

LiF BeF2 ThF4 TRUF3

73 12 11.0 4.0

73 05 16.6 5.4

83 02 10.9 4.1

80 03 12.5 4.5

Figure 7: AnF3(4) concentrations (in mole%) vs. operation time after transition to breeder mode in molten 80LiF-3BeF2-12.5ThF4 salt mixture

Figure 8: 233

U production in breeding mode

Page 8: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

8 ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012

Core/blanket metallic materials

Figure 9: Neutron spectrum on the walls separating core and blanket streams

1,0E+09

1,0E+10

1,0E+11

1,0E+12

1,0E+13

1,0E+14

1,0E+15

1,0E-03 1,0E-01 1,0E+01 1,0E+03 1,0E+05 1,0E+07

Energy, eV

Flu

x p

er

leta

rgy

unit

, n/(

s*cm

**2)

Inner blanket

wall surface

Outer blanket

wall surface

Page 9: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012 9

Figure 10: He production in Ni-Mo alloy (B content 0.001%)

Table 3: Average neutron flux in the central axial cross-section and neutron reaction rates

Location Energy group Neutron flux,

n/sm2∙s

Reaction Reaction rates,

barn∙s–1

Wall between core and inner blanket

E < 1 eV 1eV < E < 0.1 MeV

E > 0.1 MeV Total

7.7E+12 1.3E+15 2.6E+14 1.6E+15

10B(n,) 58Ni(n,) 58Ni(n,) 59Ni(n,) 60Ni(n,)

6.4E+16 9.4E+13 8.4E+11 1.9E+15 1.4E+11

Wall between core and outer blanket

E < 1 eV 1eV < E < 0.1 MeV

E > 0.1 MeV Total

4.8E+12 8.5E+14 1.7E+14 1.0E+15

10B(n,) 58Ni(n,) 58Ni(n,) 59Ni(n,) 60Ni(n,)

4.2E+16 6.0E+13 5.6E+11 1.2E+15 9.9E+10

Acknowledgements

Page 10: Molten salt reactor: Overview and perspectives

MOLTEN SALT REACTOR: OVERVIEW AND PERSPECTIVES

10 ACTINIDE AND FISSION PRODUCT PARTITIONING AND TRANSMUTATION, ISBN 978-92-64-99174-3, © OECD 2012

References


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