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MCNP simulation of salt channel in LR-0 reactor. Martin Suchopár. Nuclear Physics Institute Academy of Sciences of Czech Republic and Department of nuclear reactors Faculty of Nuclear Sciences and Physical Engineering Czech Technical University in Prague.

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mcnp simulation of salt channel in lr 0 reactor

MCNP simulation of salt channel in LR-0 reactor

Martin Suchopár

Nuclear Physics Institute

Academy of Sciences of Czech Republic

and

Department of nuclear reactors

Faculty of Nuclear Sciences and Physical Engineering

Czech Technical University in Prague

12th session of the AER Working Group F - "Spent FuelTransmutations"

and

3rd meeting of INPRO Project RMI - "Meeting energy needs in the period of raw materials insufficiency during the 21st century"

Liblice, Czech Republic, April 6 – 9, 2010

outline
Outline

Motivation – MSR and AHTR

Program EROS

Experimentalsetup

MCNP simulationsofthe salt channel

Achievedresults

Conclusion

2

ahtr and msr
AHTR and MSR
  • Molten salts have good heat-transfer properties
  • Demands on molten salts concerning their composition and properties differ in the way of their application
  • MSR (Molten Salt Reactor) uses in the primary circuit molten salts containing fissile material which serve as fuel and coolant at the same time
  • AHTR (Advanced High-Temperature Reactor) uses graphite-matrix high-temperature fuel like in helium-cooled reactors, but provides cooling with high-temperature fluoride salt without fissionable material
  • PB-AHTR (Pebble Bed Advanced High-Temperature Reactor) uses modular or integral design with high-temperature fuel pebbles filled with TRISO particles in graphite coating
program eros
Program EROS
  • EROS = Experimental zeRO power Salt reactor SR-0
  • Program serves for experimental verification of insertion zones of MSR type demonstration unit in reactor LR-0
  • Within the frame of the project SPHINX at Nuclear Research Institute (NRI) overall 5 experiments were carried out with modules denoted EROS 1 to EROS 5 inserted into the core of reactor LR-0
  • Modules differed in number and configuration of various blocks, in amount of salt and graphite contained in the core and in number and enrichment of fuel assemblies
  • Distribution of flux density and neutron spectrum in the driving zone and in salt channels were examined by 3 methods: neutron activation analysis, gama scanning method of fuel rods and thermoluminiscence detectors
  • Simulated setup is most similar to the experiment EROS 2
mcnp simulations of the salt channel
MCNP simulations of the salt channel
    • Salt channel 600 mm high surrounded with 6 shortened WWER-1000 fuel assemblies enriched with 4.4 % 235U
  • Salt channel consists of 7 sections made of aluminum
  • The sections are filled with mixture of LiF-NaF salt with the composition 60-40 molar % and the density of 1.7 g/cm3
  • LiF salt first with natural composition 92.5 % 7Li, 7.5 % 6Li, then changed to enriched 7LiF salt with 99.995 % 7Li
  • 25 experimental channels with diameter of 10 mm
  • Experimental aluminium probes with diameter of 8 mm and 3 positions for activation foils (bottom, middle, top) at height of 150, 300 and 450 mm above the bottom of the salt channel
  • Activation foils made of various activation materials with diameter of 6 mm and 50 µm thin
simulation of salt channel in mcnp
Simulationof salt channel in MCNP

Salt channelwithfuelassemblies – horizontalandverticalsectionofthesetup

simulation results 1 10 mesh tallies 1 4 salt channel filled with lif naf horizontal section
Simulationresults (1/10)meshtallies (1/4)salt channelfilledwithLiF-NaF – horizontalsection

0 – 0.5 eV

0.5 eV – 0.5 keV

0.5 keV – 10 keV

+60 cm

0

-60 cm

0

+60 cm

100 keV – 1 MeV

10 keV – 100 keV

1 MeV – 20 MeV

simulation results 2 10 mesh tallies 2 4 salt channel filled with 7 lif naf horizontal section
Simulation results (2/10)mesh tallies (2/4)salt channel filled with 7LiF-NaF – horizontal section

0 – 0.5 eV

0.5 eV – 0.5 keV

0.5 keV – 10 keV

+60 cm

0

-60 cm

0

+60 cm

100 keV – 1 MeV

10 keV – 100 keV

1 MeV – 20 MeV

simulation results 3 10 mesh tallies 3 4 salt channel filled with lif naf vertical section
Simulation results (3/10)mesh tallies (3/4)salt channel filled with LiF-NaF – vertical section

0 – 0.5 eV

0.5 eV – 0.5 keV

0.5 keV – 10 keV

+60 cm

0

-60 cm

0

+60 cm

100 keV – 1 MeV

10 keV – 100 keV

1 MeV – 20 MeV

simulation results 4 10 mesh tallies 4 4 salt channel filled with 7 lif naf vertical section
Simulation results (4/10)mesh tallies (4/4)salt channel filled with 7LiF-NaF – vertical section

0 – 0.5 eV

0.5 eV – 0.5 keV

0.5 keV – 10 keV

+60 cm

0

-60 cm

0

+60 cm

100 keV – 1 MeV

10 keV – 100 keV

1 MeV – 20 MeV

slide11

Simulation results (5/10)neutron spectra (1/2)salt channel filled with LiF-NaF – activation foils in middle positions of aluminium probes in experimental channels

channel 2

channel 4

channel 3

channel 1

slide12

Simulation results (6/10)neutron spectra (2/2)salt channel filled with LiF-NaF – activation foils in middle positions of aluminium probes in experimental channels

channel 7

channel 5

channel 8

channel 6

simulation results 7 10 reaction yields of activation materials in 7 lif naf n g reactions
Simulation results (7/10)reaction yields of activation materials in 7LiF-NaF – (n,g) reactions

upper position

lower position

middle position

simulation results 8 10 reaction yields of activation materials in 7 lif naf n p reactions
Simulation results (8/10)reaction yields of activation materials in 7LiF-NaF – (n,p) reactions

upper position

lower position

middle position

simulation results 9 10 reaction yields of activation materials in lif naf n g reactions
Simulation results (9/10)reaction yields of activation materials in LiF-NaF – (n,g) reactions

upper position

lower position

middle position

16

simulation results 10 10 reaction yields of activation materials in lif naf n p reactions
Simulation results (10/10)reaction yields of activation materials in LiF-NaF – (n,p) reactions

upper position

lower position

middle position

17

summary
Summary

Simulationsweremade as part ofresearchprojectanddiploma thesis

Experimentalsetupsimilar to EROS 2 wassimulated in MCNP

Simulationsweremadeforbothnaturaland7Li enrichedcompositionofLiF-NaF salt

9 differentactivationmaterialswerechosenforevaluatingactivationreactionyields

Achievedresults: neutron fielddistribution in the salt channel, neutron spectraandactivationreactionyields in 24 positionsforactivationfoils

18

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