Simulation of large and small fast reactors with SERPENT
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1 Simulation of large and small fast reactors with SERPENT Janne Wallenius, Erdenechimeg Suvdantsetseg, Sara Bortot Milan Tesinsky & Youpeng Zhang Reactor Physics Kungliga Tekniska Högskolan
2 R&D activities at KTH Transmutation of minor actinides in lead fast reactors Nitride fuel development Radiation damage physics ELECTRA: European Lead Cooled Training Reactor
3 Application of SERPENT Extensive use of SERPENT for calculation of reactivity coefficients in fast reactors For use in simulation of transients using SAS4A/SASSYS
4 Impact of americium on Doppler feedback Doppler constant [pcm] Am [%] Doppler feedback is reduced when introducing americium into fast reactors Coolant temperature coefficient increases Wallenius, J. Nucl. Sci. Techn, Fuel: (U0.82-x,Pu0.18,Amx)O2
5 Transient performance of sodium fast reactors 50 Permitted linear rating [kw/m] 40 Nitride 30 Metal 20 Oxide 10 Am [%] Simulation of large SFRs with oxide, nitride and metal alloy fuels made with SERPENT & SAS4A Oxide fuels are more sensitive to americium concentration. Zhang, Wallenius & Fokau: Annals Nuclear Energy 37, 2010, 629
6 Transient performance of lead fast reactors ELSY model built in SERPENT Impact of Am studied in oxide and nitride cores. Larger sensitivity to Am loading than for SFRs (larger positive coolant temperature coefficient! Nitride fuel perform better than oxides (larger margin to failure) Tesinsky, Zhang & Wallenius: Annals of Nuclear Energy 47, 2012, 104
7 ELECTRA: European Lead Cooled Training Reactor A low power fast reactor MWth Inert matrix nitride fuel - (Pu,Zr)N Heat removal by100% natural convection of liquid lead Wallenius et al, Nuclear Tecnology 177 (2012) 303 A test bed for LFR technology May be used for research on reactor dynamics Education for nuclear engineering students
8 ELECTRA: choice of fuel 40 Thermal conductivity [W/m/k] (Pu 0.4,Zr 0.6 )N (Pu,Zr)N basis for reference design + High thermal conductivity - 15 times larger than (Pu,Zr,Y)O Swelling [%] T av = 1900 K T [ C] Low fuel temperature - low swelling & low gas release + Good compatibility with lead - metal alloys dissolve in LBE 10 5 T av = 1500 K T av = 1100 K High reactivity loss - reactivity compensation required Burnup [%]
9 ELECTRA: core design & control drums 397 fuel pins, Dclad = 12.6 mm (Pu0.4,Zr0.6)N fuel. ~ 70 kg Pu from spent UOX Active core dimensions: ~ 30 x 30 cm Shutdown and reactivity compensation using 12 rotating drums with 90 B4C sectors. Suvdantsetseg, Wallenius & Bortot, Nuclear Engineering & Design 252 (2012) B4C/steel drum Modelling challenge: Rotation of drums. Serpent annular sector macrobody good tool!
10 Transient performance Single control drum rotation at BOL inserts 1.7 dollars of reactivity. Zero Doppler feedback due to hard spectrum Coolant temperature coefficient: pcm/k Fuel axial expansion coefficient: -0.4 pcm/k Radial expansion coefficient: -1.5 pcm/k Cladding creep rupture can be avoided for 1.7 dollar insertion, even for large insertion rate. Nuclear Engineering & Design 252 (2012) 209
11 Modelling challenges Overshoot Transient over power accidents are characterised by Overshoot & transition to asymptotic state Asymptotic temperature uncertainty dominated by radial expansion features. Asymptotic state In ELECTRA, uncertainty in overshoot is mainly due to calculated value of neutron generation time!
12 Neutron removal time in Serpent Neutron removal life time [µs] In lead reflected fast reactors, neutrons can survive for very long times before returning to the reactor. keff for the bare ELECTRA core = 0.7! Serpent estimate of neutron removal time θ in ELECTRA is strongly dependent of lead reflector radius! Lead radius [cm] Escape contributes significantly! Which value of Λ = θ/k should enter the point kinetics equation???
13 Neutron generation time Fission rate [1/µs] e αt Neutron generation time neutron removal time! MCNP provides estimate of neutron removal by fission. MCNP also provides possibility to simulate direct (forward) growth of neutron flux (and thus fission power), using time cut-off! Time [µs] α prompt = k promt 1 θ gen = ρ prompt Λ Alpha-eigenvalue obtained by direct simulation in an LFR pin cell is significantly smaller than fission generation time. Why? Physics behind this phenomenon may be studied by MCNP. Implementation of time-cutoff in Serpent highly desired feature!
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