cadarache sensitivity analysis of an advanced …

MAŁGORZATA WRÓBLEWSKA NCBJ - CEA – AMU

[email protected]

ANIMMA 2021 Prague, Wednesday, June 23th2021| PAGE 1

CADARACHE SENSITIVITY ANALYSIS OF AN ADVANCED MEASUREMENT METHOD FOR THERMAL

NEUTRONS ABSORBERS DETECTION IN IRRADIATED BERYLLIUM.

M. WRÓBLEWSKA, D. BLANCHET, A. LYOUSSI, P. BLAISE, Z. MARCINKOWSKA, A.BOETTCHER, J. JAGIELSKI,

JHR, FranceMARIA, Poland

SENSITIVITY ANALYSIS OF AN ADVANCED MEASUREMENT METHOD FOR THERMAL NEUTRONS ABSORBERS DETECTION IN IRRADIATED BERYLLIUM

ANIMMA 2021, Prague, June 23 2021

• Poisoning effect in MTRs

• Experimental setup

• Sensitivity analysis

• Conclusion

2


Beryllium damage mechanisms

3

6Li , 3He -> thermal neutron absorbers

3He, 4He, Tgases

Surface corrosion Defects, γ and

n0 heating

Pollution of coolant

MECHANICAL DAMAGE

REACTIVITY DECREASE

Water coolant γ and n0 flux

OVERAL DESTRUCTION

Mechanical failure examples

ATR

BR2

View of the SM and MIR reactors beryllium blocks irradiated to fast neutron fluence of F~6·1022 сm-2

V. Chakin et al., 1st International Symposium

on Material Testing Reactors. Japan. 2008.

4

JMTR samples corrosionE. H. Smith. Et. al. Symposium on material performance in operating nuclear systems. August 1973.

F. Joppen, E. Koonen, S. Van Dijck. International

Atomic Energy Agency (IAEA)

ANIMMA 2021, Prague, June 23 2021 4

Mechanical failure examples

ATR

BR2

View of the SM and MIR reactors beryllium blocks irradiated to fast neutron fluence of F~6·1022 сm-2

V. Chakin et al., 1st International Symposium

on Material Testing Reactors. Japan. 2008.

5

JMTR samples corrosion

The main criteria for mechanical damage is FAST NEUTRON FLUENCE

SAFARI ATR HFIR MARIA MIR BR-2 JMTR JHR

Max Power

[MWth]20 250 85 30 100 100 50 100

𝐁𝐞 𝚽𝒇 𝒎𝒂𝒙

[1022 n.cm-2]0.9 5.5 3.4

2.0

(>0.5MeV)

6 .0

(>0.1MeV)6.4 1.1 5.0

Be function R R R M M/R M/R R R

> 1.0MeV

~80dpa

E. H. Smith. Et. al. Symposium on material performance in operating nuclear systems. August 1973.

F. Joppen, E. Koonen, S. Van Dijck. International

Atomic Energy Agency (IAEA)

NO DETAILED IRRADIATION HISTORY


Poisons production (n,α)

Thermal neutrons

6

Fast neutronsPOISONS


Realistic scenario in MARIA

1 CYCLE = 100h on power + 68h off power10.5 YEARS OPERATION + 27 YEARS OFF

7

6Li saturation

off power periods 3He concentration increases

After 37.5 years

SPECIFIC ACTIVITY: ~1GBq /1g of Be

Simplifying assumptions; for detailed information: neutronic tools







• Conclusion

8

Experiment, analysis and validation

9

POISONS CONTENT = f-1 (DETECTOR RESPONSE)

NEUTRON SOURCE,DETECTOR,FRESH VS IRRADIATED

BERYLIUM ELEMENT,

DETECTOR RESPONSE AT GIVEN MEASURED POSITION

EXPERIMENT

MONTE-CARLO SIMULATION NEUTRON TRANSPORT

SERPENT2, JEFF3.1

SIMULATION MODEL

INVERSE PROBLEM

CALIBRATION OF THE SURROGATE MODEL

NEUTRON TRANSMISSION CONFIGURATION

DETECTOR RESPONSE = f1 (POISONS CONTENT)




Neutronsource detector

polyethylene Σ1

or

Σ2

SCATTERING

ABSORPTION

Irradiated

Non-irradiated

MEASUREMENT OF THERMAL NEUTRONS ATTENUATION IN FRESH /IRRADIATED BERYLLIUM

𝑴𝒐𝒏𝒕𝒆 − 𝑪𝒂𝒓𝒍𝒐𝒕𝒓𝒂𝒏𝒔𝒑𝒐𝒓𝒕 𝒄𝒂𝒍𝒄𝒖𝒍𝒂𝒕𝒊𝒐𝒏𝒔

𝑰𝟏𝑰𝟐= 𝒇(𝜮𝒑𝒐𝒊𝒔𝒐𝒏𝒔)


Experiment – transmission method

Beryllium block

Neutron sourceDetector

11

polyethylene



Neutron transmission

Neutron SOURCE

Neutron detector Moderator

Beryllium






• Neutron source

• Moderator

• Detector

• Conclusion

13



PuBe (239Pu/ 238Pu)

AmBe (241Am)

AmB(241Am)

SbBe (124Sb)

252Cf

0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-11 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01

Ne

utr

on

flu

x(n

/s-1·c

m-3

)

Neutron energy (MeV)

Neutron sources spectra

241AmBe

239PuBe

252Cf·104

241AmB

ISO reference spectra



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-11 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01

Ne

utr

on

flu

x(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB


0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-09 1.00E-07 1.00E-05 1.00E-03 1.00E-01 1.00E+01

Neu

tro

n f

lux

per

un

it le

thar

gy(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB

124SbBe

No moderator



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-11 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01

Ne

utr

on

flu

x(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB


0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-09 1.00E-07 1.00E-05 1.00E-03 1.00E-01 1.00E+01

Neu

tro

n f

lux

per

un

it le

thar

gy(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB

124SbBe

No moderator

1.0E+00

1.0E+01

1.0E+02

1.0E+03

1.0E+04

1.0E+05

1.0E+06

1.0E+07

1.0E+08

1.0E+09

1.0E+10

1.0E+11

²³⁹PuBe ²⁴¹AmBe ²⁴¹AmB ²⁵²Cf ¹²⁴SbBe

Rea

ctio

n r

ates

(s-1

)

Type of the neutron source

Fission chamber He3 LiF BF3



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-11 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01

Ne

utr

on

flu

x(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB


0.0E+00

5.0E+03

1.0E+04

1.5E+04

2.0E+04

2.5E+04

3.0E+04

1.00E-09 1.00E-07 1.00E-05 1.00E-03 1.00E-01 1.00E+01

Ne

utr

on

flu

x p

er u

nit

leth

argy

(n/s

-1·c

m-3

)



241AmBe239PuBe

252Cf·104

241AmB124SbBe

4.5 cm polyethylene

Moderator



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.00E-11 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01

Ne

utr

on

flu

x(n

/s-1·c

m-3

)



241AmBe

239PuBe

252Cf·104

241AmB


0.0E+00

5.0E+03

1.0E+04

1.5E+04

2.0E+04

2.5E+04

3.0E+04

1.00E-09 1.00E-07 1.00E-05 1.00E-03 1.00E-01 1.00E+01

Ne

utr

on

flu

x p

er u

nit

leth

argy

(n/s

-1·c

m-3

)



241AmBe239PuBe

252Cf·104

241AmB124SbBe

4.5 cm polyethylene

Moderator

1.0E+00

1.0E+01

1.0E+02

1.0E+03

1.0E+04

1.0E+05

1.0E+06

1.0E+07

1.0E+08

1.0E+09

1.0E+10

1.0E+11

1.0E+12

²³⁹PuBe ²⁴¹AmBe ²⁴¹AmB ²⁵²Cf ¹²⁴SbBe

Rea

ctio

n r

ates

(s-1

)

Type of the neutron source

Fission chamber He3 LiF BF3






• Neutron source

• Moderator

• Detector

• Conclusion

19



0.0E+0

1.0E+6

2.0E+6

3.0E+6

4.0E+6

5.0E+6

6.0E+6

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)

Polyethylene thickness (cm)

PuBe sourceU H LI B

U H LI B

2 differentsource spectra

0.0E+0

5.0E+6

1.0E+7

1.5E+7

2.0E+7

2.5E+7

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


AmBe sourceU H LI B

0.0E+0

5.0E+6

1.0E+7

1.5E+7

2.0E+7

2.5E+7

3.0E+7

3.5E+7

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


AmB sourceU H LI B

0.0E+0

1.0E+11

2.0E+11

3.0E+11

4.0E+11

5.0E+11

6.0E+11

7.0E+11

8.0E+11

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


CF sourceU H LI B



0.0E+0

1.0E+6

2.0E+6

3.0E+6

4.0E+6

5.0E+6

6.0E+6

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


PuBe sourceU H LI B

U H LI B

2 differentsource spectra

0.0E+0

5.0E+6

1.0E+7

1.5E+7

2.0E+7

2.5E+7

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


AmBe sourceU H LI B

0.0E+0

5.0E+6

1.0E+7

1.5E+7

2.0E+7

2.5E+7

3.0E+7

3.5E+7

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


AmB sourceU H LI B

0.0E+0

1.0E+11

2.0E+11

3.0E+11

4.0E+11

5.0E+11

6.0E+11

7.0E+11

8.0E+11

0.00 2.00 4.00 6.00 8.00 10.00

Rea

ctio

n r

ates

(s-1

)


CF sourceU H LI B

fresh poisoned


Neutron detector and source choice

22

SO

UR

CES

IN T

HE

MEA

SUR

EMEN

T SE

T (n,) on 9Be ~2MeV ~6.81MeV

activation of irradiated beryllium ~106 Bq

from the neutron source SbBe ~2.7 10-3 Gy/hr

PuBe ~2.7 10-8 Gy/hr

from radiative capture polyethylene ~2.2MeV

(,n) reactions induced by the above 1.67MeV

PuBe + fission chamber



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.4E+05

0.0E+0 2.0E+0 4.0E+0 6.0E+0 8.0E+0 1.0E+1 1.2E+1

Ne

utr

on

flu

x (n

/s-1·c

m-3

)


Various PuBe spectra

NZ010 NZ022

0.2-480 2-479

1.9-611a 4.7-555

37-425 178-461

85-701 M-99*

M-977* M-591*

M-930*

*

* Based on PuBe neutron source data from:1. M.E. Anderson, R.A. Neff, Neutron energy spectra of different size 239Pu-Be (α, n) sources. Nucl. Instr. and Meth. 99 (1972) 231-235.2. Lockhart, M.L. & McMath, G.E.. (2017). Verification of Plutonium Content in PuBe Sources Using MCNP® 6.2.0 Beta with TENDL 2012 Libraries. Physics Procedia. 90. 305-312. 10.1016/j.phpro.2017.09.016.

0.0E+00

2.0E+03

4.0E+03

6.0E+03

8.0E+03

1.0E+04

1.2E+04

1.4E+04

1.6E+04

0.0E+0 2.0E+0 4.0E+0 6.0E+0 8.0E+0 1.0E+1 1.2E+1

Ne

utr

on

flu

x (n

/s-1·c

m-3

)


PuBe spectra for 70-96% of ²³⁹Pu

Thanks to BOULAND Oliviercode iSourceC

DES/IRESNE/DER/SPRC/Physics Studies Laboratory



0.0E+00

2.0E+04

4.0E+04

6.0E+04

8.0E+04

1.0E+05

1.2E+05

1.4E+05

0.0E+0 2.0E+0 4.0E+0 6.0E+0 8.0E+0 1.0E+1 1.2E+1

Ne

utr

on

flu

x (n

/s-1·c

m-3

)


Various PuBe spectra

NZ010 NZ022

0.2-480 2-479

1.9-611a 4.7-555

37-425 178-461

85-701 M-99*

M-977* M-591*

M-930*

*

* Based on PuBe neutron source data from:1. M.E. Anderson, R.A. Neff, Neutron energy spectra of different size 239Pu-Be (α, n) sources. Nucl. Instr. and Meth. 99 (1972) 231-235.2. Lockhart, M.L. & McMath, G.E.. (2017). Verification of Plutonium Content in PuBe Sources Using MCNP® 6.2.0 Beta with TENDL 2012 Libraries. Physics Procedia. 90. 305-312. 10.1016/j.phpro.2017.09.016.

0.0E+00

2.0E+03

4.0E+03

6.0E+03

8.0E+03

1.0E+04

1.2E+04

1.4E+04

1.6E+04

0.0E+0 2.0E+0 4.0E+0 6.0E+0 8.0E+0 1.0E+1 1.2E+1

Ne

utr

on

flu

x (n

/s-1·c

m-3

)


PuBe spectra for 70-96% of ²³⁹Pu

Thanks to BOULAND Oliviercode iSourceC

DES/IRESNE/DER/SPRC/Physics Studies Laboratory

0.0E+0

1.0E+5

2.0E+5

3.0E+5

4.0E+5

5.0E+5

6.0E+5

7.0E+5

0.00 2.00 4.00 6.00 8.00 10.00

Re

acti

on

rat

es

(s-1

)


²³⁹PuBe + 235U

poliethylene density: 0.93 - 0.95 g/cm3

berylium density: 1.80 - 1.84 g/cm3

239PuBe + 235U Fission chamber


SERPENT2JEFF3.1

Conclusions

• The chosen configuration of the neutron source-moderator-detector has been tested experimentally

• We obtained good signal resolution • We still need to verify the beryllium activation and total gammas in the system• And to perform more measurements

26

ANY QUESTIONS?

THANK YOU!

27

cadarache sensitivity analysis of an advanced …

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