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An Autonomous Reactivity Control System

In The Nuclear Burning Wave Reactor

Oleksiy Fomin

National Science Center "Kharkiv Institute of Physics and Technology", Ukraine

e-mail: fomax.ua @ gmail.com

IAEA TM on Passive Shutdown Systems for LMFR Vienna, 20-22 October 2015

232Th 233Th

233Pa

233U 234U 235U 236U 237U

T½ = 22.2 min

T½ = 27 days

237Np

T½ = 6.75 days

238U 239U

239Np

239Pu 240Pu 241Pu 242Pu 243Pu

T½ = 23.5 min

T½ = 2,35 days

243Am

T½ = 4.98 hours

241Am

T½ = 14,3 years

Th-U fuel cycle

U-Pu fuel cycle

Nuclear fuel reproduction

An Autonomous Reactivity Control System In The Nuclear Burning Wave Reactor Oleksiy Fomin


Lev Feoktistov (USSR, 1988):

Nuclear Burning Wave

L.P. Feoktistov. Preprint IAE-4605/4, 1988.

L.P. Feoktistov. Sov. Phys. Doklady, 34 (1989) 1071.

Fertilezone

Breedingzone

Burningzone

Extinctionzone

Nuclearasheszone

238U (n,) 239U () 239Np () 239Pu (n,fission) ... T1/2 2.35 days

Concept & Analytical approach

Feoktistov

criterion

2

8 8 Pu2 Pua a f

n nD vn N N

t z

88 8 ;a

Nvn N

t

98 8 9

1a

Nvn N N

t

Pu9 PuPu

1a f

NN vn N

t

x z Vt 8 8Pu a

eq Pu Pu

f a

NN

( 1)

ai iPu icr Pu

f

NN

Pu Pu

eq crN N

Goldin & Anistratov (USSR, 1992): Nuclear Burning Wave Deterministic approach

V. Goldin, D. Anistratov. Preprint IMM RAS # 43 U-Pu fuel cycle 1d non-stationary problem

Edward Teller (USA, 1997): Traveling Wave Reactor Monte Carlo simulation

E.Teller. Preprint UCRL-JC-129547, LLNL Th-U fuel cycle

Hiroshi Sekimoto (Japan, 2001): CANDLE Deterministic approach

H.Sekimoto et al., Nucl. Sci. Eng., 139, 306 U-Pu fuel cycle Stationary problem: x = z + Vt

238U

239Pu

Fission Products

NBW Fuel Burn-Up



L z

r

R

L

ign

j ext

Breeding zone

Ignition zone

238 U 100 % 238 U

90 %

239 Pu

10 %

2D Non-Stationary Theory of Nuclear Burning Wave

S. Fomin, Yu. Mel’nik, V. Pilipenko, N. Shul’ga, A. Fomin (1st IC “Global 2009”, Paris, paper 9456)

Nuclear Burning Wave

/ / / / / /

/ / /

1 1

1

1 1 1

1 1

( ) ( )

g g gg g g g g g g g g g

a in mod in modg

gG Gg g g j j g g j j j g g g

f f f d l f f l d l l inj l j lg g g

rD Dv t r r r z z

C

( 1) ( 1) ( 1)

g gg glal l l c l l l

g g

NN N

t

Non-Stationary Nonlinear Multi-Group Diffusion Equation of Neutron Transport

Together with Fuel Burn-up Equations and Equations of Nuclear Kinetics

of Precursor Nuclei of Delayed Neutrons

96 6

NN

t

10

1,4,5,6,7

gg

fl l

l g

NN

t

( )j

j j j g g gll l l f f l

g

CC

t

Metal fuel (44%)

Pb-Bi coolant (36%)

CM - Fe (20%)

jext ~ 1015 cm-2 s-1

toff = 400 days

( 1 8);, l

Example: Metallic fuel 232Th (62%) + 238U (38%) volume fraction = 55%,

fuel porosity p = 0.20; Coolant (Pb-Bi eutectic) vol. frac. = 30%,

Constr. materials (Fe) vol. frac. = 15%; R = 215 cm

L z

r

R

L зап

Jext

Breeding zone

Ignition zone

238 U 50 % 238 U

90 %

239 Pu

10 %

232Th 50 %



NBW reactor with mixed Th-U-Pu fuel cycle

Fuel burn-up for Th-U-Pu cycle



Reactor composition (vol. frac.):

Fuel = 55% (FTh = 62%, p = 0.20), Coolant = 30%, CM = 15%, R = 215 cm

- negative feedback on reactivity - intrinsic safety

- long-term (decades) operation without refueling and external control

- possibility of 232Th and 238U utilization as a fuel

- fuel burn-up depth for both 238U and 232Th ≈ 50%

- neutron flux in active zone ≈ 2·1015 n/сm2s

- neutron fluence during the whole reactor campaign ≈ 3·1024 n/сm2

- energy production density in active zone ≈ 200 W/сm3

- total power at the steady-state regime ≈ 1.2 GW

- wave velocity at the steady-state regime ≈ 2 сm/year

- possibility of nuclear waste burn out (expected)



Main features of NBW reactor with mixed Th-U-Pu fuel cycle

Perturbation of integral neutron flux Fint (1022 cm/s) caused by an external neutron source

via time t (days). The source with intensity Qext = 21011 (cm-3 s-1) starts at t0 = 0 days,

lasts during 1 hour and is situated at 160 < z < 170 cm

-10 0 10 20 30 40 50 60 70 80

5

10

15

20

25

30 a)

int

t-t0

Stability of the NBW Regime

R = 230 cm

≈ 2.5 days



Evolution of the volume-averaged neutron flux Fav (1015 cм-2 с-1) and concentrations Nav (1017 cm-3)

of the main fissile and intermediate nuclides in the fuel of mixed ThUPu cycle with time t (days) at the

initial stage of the neutron flux perturbation t0 = 3650 days. The averaged nuclide concentrations: NNp

is for 239Np, NPa = NPa - 53.1·1017 cm-3, is for 239Pu is for 233U.

-1 0 1 2 3 4 5 6 7 8

1

2

3

4

t - t0

av

0

1

2

4

5

6

7

8

~

~

NNp

NPa

NPu

NU

~

Nav

av

Negative Reactivity Feedback: Stability of the NBW Regime

0Pu Pu Pu 1t

N N N

0

U U U 1,

tN N N

≈ 2.5 days



Variation of the reactivity ρ (dollars) with time t (days)

along the variation of the volume-averaged neutron flux Fav (1015 cм-2 с-1)

Negative Reactivity Feedback: Stability of the NBW Regime

-1 0 1 2 3 4 5 6 7 8

1

2

3

4

t - t0

av

-0.20

-0.15

-0.10

-0.05

0.00

0.05

0.10

0.15

0.20

av



Temperature and Power Analysis (U-Pu cycle)



Temperature and Power Analysis





ARC respond to ULOHS



ARC and NBW interaction at ULOHS



ARC at NBW Restart



ARC and NBW Feedback at Cooling Restart

Our publications:

S. Fomin et al., Annals of Nuclear Energy, 32 (2005) 1435-1456.

S. Fomin et al., Problems of Atomic Science & Technology, 6 (2005) 106-113.

S. Fomin et al., Nuclear Science & Safety in Europe. Springer (2006) 239-251.

S. Fomin et al., Problems of Atomic Science & Technology, 3 (2007) 156–163.

S. Fomin, Reactor Physics and Technology. PINP WS, St-Perersburg, XL-XLI (2007) 154-198.

S. Fomin et al., Progress in Nuclear Energy, 50 (2008) 163-169.

Yu.Mel’nik et al., Atomic Energy, 107 (2009) 288-295.

S. Fomin et al., Progress in Nuclear Energy, 52 (2011) 800-805.

O. Fomin et al., Proc. Of Glodal 2015, September 20-24 (2015) Paris, Paper 5254.

Our conference activity:

2005 ICENES (Brussels, Belgium) IC058; NATO-ARW NSSE (Yalta, Ukraine); IAEA-RCM ADS (Minsk, Belarus)

2006 ICAPP’06 (Reno, USA) paper 6157; NPAE (Kiev); QEDSP’06 (Kharkov); INES-2 (Yokohama, Japan)

2007 ICAPP’07 (Nice, France) paper 7499; WS PINP (St-Perersburg, Russia); IAEA-RCM ADS (Roma, Italy)

2008 Channeling’08 (Erice, Italy); NATO-ARW SNE (Yalta, Ukraine) | NPQCD (Dnepropetrovsk, Ukraine)

2009 IAEA-RCM ADS (Vienna, Austria), ANIMMA (Marseille, France); Global 2009 (Paris, France) paper 9456

2010 IAEA-RCM ADS (Mumbai, India); PINP WS (St-Perersburg, Russia); ICAPP (San Diego, USA) paper 10302

NPAE (Kiev); IAEA-TWG-FR (Brussels, Belgium); 19 ICPRPRMS (Alushta, Ukraine); INES-3 (Tokyo, Japan)

2011 IAEA-TWG-FR (Beijing, China); NSC KIPT SS (Alushta, Crimea); QEDSP’11 (Kharkov, Ukraine);

IAEA-TWG-FR (Chinnai, India); IAEA-TWG-FR (Vienna, Austria)

2012 IAEA-TWG-FR (Vienna, Austria); IAEA-TWG-FR (Argonne, USA); NPAE-4(Kiev , Ukraine) 2013 FR13 (Paris, France)



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