nuclear data needs for myrrha and minerva · 2019. 6. 12. · nuclear medicine and medical...

Nuclear data needs for MYRRHA and MINERVA

Peter Baeten

SCK•CEN, Blegium

OECD/NEA, June 6th, 2019

Copyright © 2019 SCK•CEN

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Outline

• MYRRHA & MINERVA

• Needs for Criticality Safety

• Needs for Shielding

• Needs for Radioactive Source Terms & Waste Management


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MYRRHA

Source: SCK•CEN MYRRHA Project Team, MYRRHA Business Plan

Construction of an

Accelerator-Driven

System (ADS)

consisting of

A 600 MeV, 4 mA

proton linear

accelerator

A spallation

target/source

A lead-Bismuth

Eutectic (LBE)

cooled reactor

able to operate

in subcritical &

critical mode

ECR source

& Injector

Building

MYRRHA LINAC

high energy tunnel

MYRRHA

reactor

building

Utilities

buildings

BR2 reactor

(existing)

Accelerator

particles protons

beam energy 600 MeV

beam current up to 4 mA

Reactor

power 65 to 100 MWth

keff 0,95

spectrum fast

coolant LBE

Target

main reaction spallation

output 2·1017 n/s

material LBE (coolant)

Key technical objective: An Accelerator Driven System

Demonstrate the ADS concept at pre-industrial scale

Can operate in critical and sub-critical modes

Demonstrate transmutation

Fast neutron source multipurpose and flexible

irradiation facility

https://ecm.sckcen.be/webdav/nodes/33769409/myr010000_Old.mov


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Belgium decided to build a new large research

infrastructure MYRRHA to remain at the forefront

worldwide in :

Transmutation (Partitioning & Transmutation) of radioactive

waste.

Nuclear medicine and medical radioisotope production

Demonstrate ADS technology

Research in new materials

Contribute to development of lead fast reactors

Applications of MYRRHA

September 7, 2018: Belgian government decided to

finance (558 M€) design, construction and operation of

MYRRHA for the period 2019 – 2038

Source: SCK•CEN MYRRHA Project Team


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MYRRHA’s phased implementation strategy

70kWdump#1

Spokelinac352.2MHz48cav.,l=73m

80—100MeV17MeV5.9MeV1.5MeV0.03MeV

LEBT4-rodRFQthermalmockup SC-CHcavity

RT-CHcavity

LEBT RFQ RT-CHsec on SC-CHsec onMEBT

SC-CHcavity

singlespokecavity

spokecryomodule

powercoupler

#2

coldtuningsystem

5elementellip calcavity

ellip calcavityenvelopewithcoldtuning

mechanism designofthetestcryomodulefortheellip calcavity

700MHzSolidStateRFamplifierprototyping

Ph

ase

1 –

10

0 M

eV

Source:SCK•CEN MYRRHA Project Team

Ph

ase

2 –

60

0 M

eV

Ph

ase

3 –

Reacto

r

Benefits of phased

approach:

• Reducing

technical risk

• Spreading

investment cost

• First R&D facility

available in Mol

end of 2024


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o MINERVA (MYRRHA Isotopes productioN coupling the linEar acceleRator

to the Versatile proton target fAcility)

Build and test the first part of the MYRRHA accelerator, up to 100 MeV.

Extreme reliability of accelerator is required:

- Less than 10 beam trips longer than 3 sec per 3-month

operation period,

- Less than 100 beam trips longer than 0.1 sec per day,

- Mean Time between Failures MTBF > 250 hrs.

Design, build and operate a 100 MeV Proton Target Facility (PTF)

o Production of radioisotopes - ISOL

- Fundamental physics experiments

- Innovative medical isotopes production

o Structural material irradiation (eg. for fusion applications)

o MYRRHA reactor design and research on-going in parallel

Source:SCK•CEN MYRRHA Project Team

MYRRHA Phase 1: ongoing

Consists of


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Outline






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Criticality uncertainties

Increase of confidence by improving the uncertainties is needed for

239Pu: (n,) both in resonance and fast energy region, (n,f) fast, and ҧ𝜐 fast

238U: (n,n’) fast, (n,) resonance and fast, (n,n) resonance and fast

56Fe: (n,) resonance and fast

235U: ҧ𝜐 , (n,f), (n,) resonance and fast

209Bi (n,) and (n,n’) resonance and fast

208Pb (n,n) and (n,n’) resonance and fast

241Pu (n,f) resonance and fast

242Pu (n,f) fast

240Pu: ҧ𝜐 fast

238Pu: (n,f) both resonance and fast

239Pu(n,f) reaction rate can be measured

in VENUS-F with the spectrum close to

MYRRHA one (see further)

Total 𝑘𝑒𝑓𝑓𝑘𝑒𝑓𝑓

= 0.945% ~1000 pcm

Target accuracy :𝑘𝑒𝑓𝑓𝑘𝑒𝑓𝑓

300𝑝𝑐𝑚 (<eff)


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Needs in Plutonium data

Source: R. Capote (IAEA), Presentation given at ND2019, Beijing, 24th May 2019, L450

R. Capote (IAEA) @ ND2019, Beijing, 24th May 2019: Importance of reliable Pu evaluation


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Challenges: Pu-241 example

106 107

1.0

1.5

2.0

2.5

ENDF/B-VII.1

JENDL-4.0

JEFF-3.2

Tovesson+, 2010

Desai+, 2013

24

1P

u f

issio

n c

ross s

ectio

n,

b

E, eV

106 107

1.0

1.5

2.0

2.5

ENDF/B-VII.1

JENDL-4.0

JEFF-3.2

Tovesson+,2010

Desai+,2013

Butler+,1961

Kazarinova+,1961

White+,1967

Smith+,1969

Kaeppeler+,1973

Szabo+,1973

Fursov+,1977

Khan+,1979

Aleksandrov+,1983

Fomushkin+,1997

24

1P

u fis

sio

n c

ross s

ection, b

E, eV

Recent experimental data +old experimental data

Only recent experimental data

considered: libraries

overestimate

+old data: consistency of libraries

with many data sets


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Integral validation: VENUS-F

VENUS-F zero power reactor coupled

to GENEPI -3C deuteron accelerator

(14 MeV neutrons from D+T)

1E-8

1E-7

1E-6

1E-5

1E-4

1E-3

1E-2

1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 1E-2 1E-1 1E+0 1E+1

Ne

utr

on

sp

ect

rum

Neutron energy [MeV]

total corefuelcoolant

1E-6

1E-5

1E-4

1E-3

1E-2

1E-8 1E-7 1E-6 1E-5 1E-4 1E-3 1E-2 1E-1 1E+0 1E+1

Re

acti

on

rat

e in

fu

el

Neutron energy [MeV]

235U(n,f)

238U(n,f)

235U(n,g)

238U(n,g)

30% U metallic fuel + Pb “coolant” (solid

Pb, alternatively Bi)

Pb reflector

SS


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Criticality C/E

Source: A. Kochetkov, 2019

9 core configurations

studied within EU

Projects

FREYA, MYRTE,

MIRACL, MIPSA in

2011-2019

Core #FAs FA composition Reflector In-Pile Section

CR0 97 9 U+16 Pb Pb -

CC5 41 13 U+8 Pb+4 Al2O3 Pb -

CC6 41 13 U+8 Pb+4 Al2O3 Pb -

CC7 41 13 U+8 Pb+4 Al2O3 Pb+C -

CC8 47 13 U+8 Pb+4 Al2O3 Pb+C thermal spectrum

CC9 41 13 U+8 Bi+4 Al2O3 Pb -

CC10 41 13 U+Pb+8 Bi+4 Al2O3 Pb+C -

CC10b 47 13 U+Pb+8 Bi+4 Al2O3 Pb+C thermal spectrum

CC11 50 13 U+Pb+8 Bi+4 Al2O3 Pb+C thermal and fast spectrum

Besides criticality C/E, we have:

Kinetic parameters

CR curve

Spectral indices

Axial and radial traverses

Pb-Bi void

Fuel Doppler

Extensive database for ND

validation !

208Pb

0.269

208Pb(n,el)

0.26956Fe(n,el)

0.226

235U

0.205

235U(n,f)

0.269 238U(n,)

0.223

235U(n,)

0.182

%k/k

Sensitivity analysis shows large contribution of 208Pb elastic scattering

and average scattering angle cosine

These data for 208Pb are very close to each other in all the libraries


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Outline






14SCK•CEN/34183990

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Beam line at the Centre des Ressources du Cyclotron in

Université Catholique de Louvain

70kWdump#1

Spokelinac352.2MHz48cav.,l=73m

80—100MeV17MeV5.9MeV1.5MeV0.03MeV

LEBT4-rodRFQthermalmockup SC-CHcavity

RT-CHcavity

LEBT RFQ RT-CHsec on SC-CHsec onMEBT

SC-CHcavity

singlespokecavity

spokecryomodule

powercoupler

#2

coldtuningsystem

5elementellip calcavity

ellip calcavityenvelopewithcoldtuning

mechanism designofthetestcryomodulefortheellip calcavity

700MHzSolidStateRFamplifierprototyping

RFQ ~ 4155 mm MEBT-1 and CH1-CH7 ~ 7108 mmIS+LEBT ~ 3712 mm 922 mm

1.5 MeV 5.9 MeV

IS – ion source

LEBT – low energy beam transport, up to 30 keV

RFQ - radio frequency quadrupole, up to 1.5 MeV

MEBT – medium energy beam transport and

CH – cross-bar H-type cavities, up 5.9 MeV

SCK•CEN

CRC UCL


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5.9 MeV beam dump shielding

Source: JEFFDOC-1956, 2018

Beam dump

5.5 6.0 6.5 7.0

10-4

10-3

10-2

10-1

Blaser+, 1951

Bubb+, 1965

Sekharan+, 1976

Fynn+, 1978

Cheng+, 1980

ENDF/B-VIII.0

JENDL-4/HE

PADF-2007

JEFF-3.3 (TENDL2017)Ne

utr

on

pro

ductio

n c

ross s

ectio

n,

mb

Energy, MeV

Threshold = 5.804 MeV

p+27Al

No data on neutron production in JEFF

between 5.8 (threshold) and 6 MeV

0.0 0.2 0.4 0.6 0.8 1.0 1.210-1

100

101

102

103

104

105

106

107

neutron

H*

(10

) [

Sv

/h]

Shield thickness (m)

JEFF-3.3 (TENDL-2017)

JEFF-3.3 (TENDL-2017) with corrected 27Al(p,x)n near threshold

JEFF-3.3 (TENDL-2017) with 27Al(p,x)n from PADF-2007

concrete block 1 concrete block 2 air


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MINERVA: Shielding of 100 MeV accelerator +

target for fusion materials irradiation

Source: JEFFDOC-1956, 2108

2 4 6 8 10 12 14 16 18 20

0.0

2.0x10-3

4.0x10-3

p+natC Blaser+, 1951

Gibbons+, 1959

Wong+, 1961

Ramstroem+, 1976

Bair+, 1981

Kitwanga+, 1989

Firouzbacht+, 1991

JEFF-3.3 (TENDL-2017) corr

JENDL-4/HE corr

Model calc INCL+GEM (PHITS)

Model calc Bertini+GEM (PHITS)

Neutr

on p

roduction c

ross s

ection, b

Energy, MeV

Thresholds:

12C(p,x)n = 19.642 MeV

13C(p,x)n =3.236 MeV

10-4 10-3 10-2 10-1 100 101 102

10-8

10-7

10-6

10-5

10-4

10-3

10-2

JEFF-3.3 proton-induced

ENDF/B-VIII.0 proton-induced

Neutr

on flu

ence, n/c

m2/M

eV

/s.p

.

Neutron energy, MeV

Neutron spectra from p(100 MeV) + W

Shielding of ISOL targets:

Huge discrepancies between

libraries/experimental data, especially

for protons + light nuclei

Material irradiation (fusion targets):

Huge discrepancies both in neutron

spectra and total neutron yield from

p+W


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Outline






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Polonium-210 in MYRRHA

Produced by neutron capture

Assuming no release, during 1 irradiation cycle 5.5e+4 TBq of 210Po is

produced from ~7600 ton of LBE

Decay heat: 48 kW of LBE pool

Normal operation: partially migrates in cover gas

Failures or leaks: evaporation in contact with ambient air, formation of

highly volatile species in presence of moistures and/or hydrogen

Accurate prediction of 210Po production by neutronic codes is needed

𝟖𝟑𝟐𝟎𝟗𝑩𝒊

(𝒏,)𝟖𝟑

𝟐𝟏𝟎𝑩𝒊𝟓.𝟎𝟏𝟑𝒅,𝜷−

𝟖𝟒𝟐𝟏𝟎𝑷𝒐

𝟏𝟑𝟖𝒅,𝛂

𝟖𝟐𝟐𝟎𝟔𝑷𝐛

JE

FF

-3.1

.2

RO

SF

ON

D-1

0

EA

F-1

0

JE

FF

-3.2

BR

ON

D-3

.1

JE

FF

-3.3

JE

ND

L-4

.0

TE

ND

L-1

0

TE

ND

L-1

1

TE

ND

L-1

2

TE

ND

L-1

4

TE

ND

L-1

7

JE

FF

-3.1

.2g

RO

SF

ON

D-1

0g

EA

F-1

0g

JE

FF

-3.2

g

BR

ON

D-3

.1g

JE

FF

-3.3

g

JE

ND

L-4

.0g

CE

ND

L-3

.1g

EN

DF

/B-V

III.

0g

TE

ND

L-1

0g

TE

ND

L-1

1g

TE

ND

L-1

2g

TE

ND

L-1

4g

TE

ND

L-1

7g

-40

-20

0

20

40

60

80

100

g=100% capture to 210gBiC

/Re

f -

1,

%Ref=JEFF-3.1.2 Grey shadow:

consideration of

neutron capture to

ground state only =

maximum possible 210Po production

Available covariance

data have been

propagated for some

libraries

The uncertainties do

not cover differences

between libraries


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Polonium-210 in MYRRHA

10-2

100

102

104

106

0

5

10

15 JENDL/A-96

RUSFOND-2010

JENDL-4.0

JEFF-3.2

BROND-3.1

g /

m

Neutron energy / eV

Borella et al. (Budapest)

Borella et al. (GELINA)

Saito et al.

Yield (branching ratio)

A new experimental programme to measure BR and total neutron

capture was launched by JRC and SCK•CEN

First measurements have been performed in 2019 at J-PARC/ANNRI

(Japan)

They will be complemented by measurements at GELINA (JRC)

A new entry added to High Priority Request List


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Conclusions

To design and license MYRRHA and its Phase I MINERVA, reliable nuclear

data with covariances are needed to provide reliable central values and

uncertainties for safety related parameters: criticality, reactivity effects,

shielding, waste management, radioactive source terms, etc.

For criticality safety, we need to reduce the keff uncertainty from ~1000 to

300 pcm (< 1 eff)

For shielding design for MINERVA, reliable proton-induced data,

especially for light nuclides, are required

For waste management, one of key points is accurate prediction of Po-210

production: an experimental programme has been launched with ultimate

goal to produce new JEFF evaluation for Bi-210


21SCK•CEN/34183990

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A jump in the future for innovation in Belgium


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Copyright © 2019 - SCKCEN

PLEASE NOTE!

This presentation contains data, information and formats for dedicated use ONLY and may not be copied, distributed or

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communication. By courtesy of SCK•CEN”.

SCK•CEN

Studiecentrum voor Kernenergie

Centre d'Etude de l'Energie Nucléaire

Belgian Nuclear Research Centre

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Fondation d'Utilité Publique

Foundation of Public Utility

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nuclear data needs for myrrha and minerva · 2019. 6. 12. · nuclear medicine and medical...

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