Update of uncertainty file in the EAF project

J. Kopecky1 and R.A. Forrest2

1JUKO Research, the Netherlands2EURATOM/UKAEA Association,

Culham, UK

FENDL Vienna 2-5.12.2008

Scope of the presentation

● History of EAF uncertainties

● EAF-2007 status

● Current actions and updates for EAF-2009

● Conclusions

History of EAF uncertainties

● EAF-2 (1991) - Use of error factors derived from 14.5 MeV systematic to assess the overall uncertainty for most of the reactions. These factors indicate the accuracy estimate only.

Reaction Systematic Uncertainty Error Estimate treatment

(n,n) Vonach 1.5 (n,2n) THRESH 1.2 (n,3n) 0.8*THRESH 2.0 (n,n) 0.125*(n,) 3.0 (n,d) + (n,n’p) Forrest 2.0 (n,np) nd+nnp) - nd) 2.0 (n,t)+(n,nd) Forrest 1.6 (n,t) 0.9*nt+nnd) 1.6 (n,n’t) - (n,nh) - (n,) Kopecky 1.5 (n,p) Forrest 1.5 (n,h) Forrest 1.9 (n,) Forrest 1.6 (n,2p) 0.75*nt) 3.0

History of EAF uncertainties (cont.)

● EAF-3 (1992) – Uncertainty file (in the ENDF-6 MF = 33 format) for all reactions in a 1 group (threshold reactions [Eth–20MeV]) and 2 groups (non-threshold

reactions [10-5eV–EH–20MeV]) structure. The uncertainty values adopted correspond to the error factor f = 1 + , where is the relative error (2 is actually stored in the file) in the cross section . In this case the best estimate of the cross section uncertainty is /f < < f.

TI- 48N,2N 224833 16 2.20480E+4 4.7536E+01 0 0 0 1224833 16 0.0000E+00 0.0000E+00 0 16 0 1224833 16 0.0000E+00 0.0000E+00 0 1 6 3224833 16 1.0000E-05 0.0000E+00 1.1875E+07 4.0000E-04 2.0000E+07 0.0000E+00224833 16 224833 0 TI- 48N,NA 224833 22 2.20480E+4 4.7536E+01 0 0 0 1224833 22 0.0000E+00 0.0000E+00 0 22 0 1224833 22 0.0000E+00 0.0000E+00 0 1 6 3224833 22 1.0000E-05 0.0000E+00 9.6386E+06 4.0000E+00 2.0000E+07 0.0000E+00224833 22 224833 0 TI- 48N,NP 224833 28 2.20480E+4 4.7536E+01 0 0 0 1224833 28 0.0000E+00 0.0000E+00 0 28 0 1224833 28 0.0000E+00 0.0000E+00 0 1 6 3224833 28 1.0000E-05 0.0000E+00 1.1683E+07 1.0000E+00 2.0000E+07 0.0000E+00224833 28 224833 0 TI- 48N,G 224833102 2.20480E+4 4.7536E+01 0 0 0 1224833102 0.0000E+00 0.0000E+00 0 102 0 1224833102 0.0000E+00 0.0000E+00 0 1 8 4224833102 1.0000E-05 1.1696E-01 1.0000E+03 2.7889E-02 1.0000E+05 1.0000E+00224833102 2.0000E+07 0.0000E+00 224833102 224833 0 TI- 48N,P 224833103 2.20480E+4 4.7536E+01 0 0 0 1224833103 0.0000E+00 0.0000E+00 0 103 0 1224833103 0.0000E+00 0.0000E+00 0 1 6 3224833103 1.0000E-05 0.0000E+00 3.2793E+06 2.5000E-03 2.0000E+07 0.0000E+00224833103 224833 0 TI- 48N,D 224833104 2.20480E+4 4.7536E+01 0 0 0 1224833104 0.0000E+00 0.0000E+00 0 104 0 1224833104 0.0000E+00 0.0000E+00 0 1 6 3224833104 1.0000E-05 0.0000E+00 9.4122E+06 1.8490E-01 2.0000E+07 0.0000E+00224833104 224833 0

MF33 from EAF-3

Error factors (EAF-3) Used for all reactions

Reaction Systematic Uncertainty factor f

Comment

(n,n) Vonach 1.5 (n,2n) THRESH 1.2 (n,3n) Estimate 3.0 0.8*THRESH (n,4n) Estimate 3.0 (n,n) Estimate 3.0 0.125 * (n,) (n,d) + (n,np) Forrest 2.0 (n,t) + (n,nd) Forrest 1.6 (n,nt) Estimate 5.0 (n,nh) Estimate 5.0 (n,f) Estimate 1.5 Model calcul. (n,f) Estimate 3.0 Behrens syst. (n,) Kopecky 1.5 (n,p) Forrest 1.5 (n,h) Forrest 1.9 (n,) Forrest 1.6 (n,2p) Estimate 2.5 0.75 * (n,t)

History of EAF uncertainties (cont.)

● EAF-4 (1995) ● The uncertainty file contained more information for (n,) and

(n,f) reactions. These were given in 3 groups (10-5eV – EL – EH–20MeV]) rather than the 2 groups used previously. (th) and Iare used for respective energy groups as an experimental information.

● Estimates for data with no experimental information :

Reaction Region Error factor (f) (n,) 1/v 10.0 (n,) EL - EH 2.0 (n,) EH – 20MeV 1.5 (n,f) 1/v 5.0 (n,f) EL - EH 3.0 (n,f) EH – 20MeV 2.0

History of EAF uncertainties (cont.)

● Experimental uncertainties for threshold reactions (EAF data set of recommended single (14.5 MeV) data points) were used to replace the generic values adopted from 14.5 MeV systematic. This 14.5 MeV experimental variance is used for the entire energy range of the excitation function, and because no information on uncertainties at other energies has been used, an uncertainty value of = 3exp has been adopted if <

0.25.

History of EAF uncertainties (cont.)

● EAF-97 (1997) - New treatment of uncertainties for split reactions has been adopted. If experimental values of partial cross sections are known their uncertainties are adopted. However, in general for uncertainties of cross sections to ground and isomeric states an uncertainty factor of the branching ration (fb) of 1.3 has been adopted when the

branching is derived from BR systematic. ● By definition m = band g = (1-b). Thus the uncertainty in

m is given by and =f-1 and b=fb -1.

Thus .

222

b

b

m

m

)1(21 22 bbgm ffffff

History of EAF uncertainties (cont.)

● EAF-99 (1999) - EAF-2001 (2001) - EAF-2003 (2003) - The corresponding uncertainty files for reactions supported with experimental data includes visual estimates based on all EXFOR data points covering broader energy regions. Three energy groups have been applied also for non-threshold (n,p) and (n,) reactions with LEA treatment below EH.

Error factors (EAF-97 – EAF-2003) Used for all reactions with no experimental support

Reaction Systematic Error factor (f) 1997 - 2003

(n,n) Vonach 1.5 -> 2.0 (n,2n) Badikov 1.2 -> 1.4 (n,3n) Estimate 3.0 (n,4n) Estimate 3.0 (n,n) Estimate 3.0 (n,d)+(n,np) Forrest 2.0 -> 3.0 (n,np) Kopecky 2.0 (n,t)+(n,nd) Forrest 1.6 (n,nt) Estimate 5.0 (n,nh) Estimate 5.0 (n,f) Estimate (calc) 1.5 -> 2.0 (n,f) Estimate (syst) 3.0 (n,) Kopecky 1.5 -> 2.0 (n,p) Forrest 1.5 (n,h) Forrest/Lishan 1.9 (n,) Forrest/Madjdedin 1.6 (n,2p) Estimate 3.0

History of EAF uncertainties (cont.)● EAF-2005 – The upper energy extended to 60 MeV by adding

a new energy group (20 – 60 MeV). The new error factors have been adopted using the assumption of f < 20MeV = f > 20 MeV.

● Threshold reactions:

Zn-64(n,2n)Zn-63

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

8.0E-02

1.6E-01

2.4E-01

3.2E-01

4.0E-01

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmRI 99TEX75SST87RAM83AUW78LOU73ANL87NMX88ARK76JYV76JUL72BOS69RAB91JAE93AUB95TOH92TOH68RI 99HAM63PTB04KTY65

Eth 20MeV

60MeV

Mn-55(n,a)V-52

Final

Cro

ss s

ect

ion (

b)

Energy (eV)

0.0E+00

7.0E-03

1.4E-02

2.1E-02

2.8E-02

3.5E-02

0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20KOS93MUA65TUD84ELU80LOU78KIG84TUR67IRK65ORL65GEL00GEL00JUL94RI 99IBJ80IBJ75

Eth

20MeV

60MeV

Uncertainties – non-threshold reactions

Ni-60(n,g)Ni-61

Final

Cro

ss s

ection (

b)

Energy (eV)

1.0E+03

1.0E-04

1.0E-03

1.0E-02

1.0E-01

1.0E+00

1.0E+01

1.0E+02

6.0E+071.0E-04 1.0E-03 1.0E-02 1.0E-01 1.0E+00 1.0E+01 1.0E+02 1.0E+03 1.0E+04 1.0E+05 1.0E+06 1.0E+07

SystmSys30ROS71ORL04IPE97ORL52MCM77KFK84KFK84ORL82RPI71GEL02

EL

EHEL

20MeV

60MeV(th)

Ior 0.5

expor 0.5

EAF-2007 status (exp. data)

● Error factors based on experimental data -The experimental variance is adopted from both EXFOR as well the EAF internal data base and is used for the entire energy range of the excitation function. This uncertainty has been estimated visually from the data scatter around the library excitation curve from cross section plots or from growing data base of experimental integral validations.

EAF-2007 status (no exp.)● Error factors with no experimental data (based on (14.5

MeV) systematic - These factors quantify how well the systematic of (14.5 MeV) fits the experimental data. They are used in the generation of the uncertainty file if no experimental data are available and the adopted library data agree with (14.5 MeV). They are assumed to be representative for the whole energy range above Eth and the conservative values are applied.

● Error factors f without systematic - If no cross section systematic is available, the results of graphical treatment of calculations or adopted data (e.g. SACS analysis) and the educated conservative guess of the accuracy of the calculation (upper limit) are applied.

● Error factors f > 20 MeV - If no experimental data are available to estimate f, the same uncertainty is adopted as the uncertainty of the energy group just below 20 MeV.

Error factors EAF-2007 Used for all reactions with no experimental support

Reaction Systematic Error factor (f) (n,n) Vonach] 2.0 (n,2n) Badikov 1.4 (n,3n) Estimate 3.0 (n,4n) Estimate 3.0 (n,n) Estimate 3.0 (n,d) Forrest 3.0 (n,np) 2.0 (n,t)+(n,nd) Forrest 1.6 (n,nt) Estimate 5.0 (n,nh) Estimate 5.0 (n,f) Estimate 2.0 (n,) Kopecky 2.0 (n,p) Forrest 1.5 (n,h) Lishan 1.9 (n,) Madjdeddin 1.6 (n,p) Estimate 3.0 (n,2p) Estimate 3.0 (n,n2p) Estimate 3.0 (n,2) Estimate 3.0 (n,3) Estimate 3.0 (n,2np) Estimate 3.0 (n,2nd) Estimate 3.0 (n,pd) Estimate 3.0 (n,pt) Estimate 3.0 (n,d) Estimate 3.0 (n,3n) Estimate 3.0 (n,3np) Estimate 3.0 (n,n2) Estimate 3.0 (n,d2) Estimate 3.0 (n,t2) Estimate 3.0 (n,n3) Estimate 3.0 (n, nd2) Estimate 3.0 (n, nt2) Estimate 3.0 (n,2n2) Estimate 3.0 (n,2n) Estimate 3.0 All remaining ‘high-energy’ reactions

Estimate 3.0

(n,2p) Estimate 3.0 (n,n2p) Estimate 3.0 (n,2) Estimate 3.0 (n,3) Estimate 3.0 (n,2np) Estimate 3.0 (n,2nd) Estimate 3.0 (n,pd) Estimate 3.0 (n,pt) Estimate 3.0 (n,d) Estimate 3.0 (n,3n) Estimate 3.0 (n,3np) Estimate 3.0 (n,n2) Estimate 3.0 (n,d2) Estimate 3.0 (n,t2) Estimate 3.0 (n,n3) Estimate 3.0 (n, nd2) Estimate 3.0 (n, nt2) Estimate 3.0 (n,2n2) Estimate 3.0 (n,2n) Estimate 3.0 All remaining ‘high-energy’ reactions

Estimate 3.0

References prior EAF-2009

● J Kopecky, D Nierop and RA Forrest, Uncertainties in the european activation file EAF-3.1, ECN-C—94-015 (March 1994).

● RA Forrest, J Kopecky, Statistical analysis of cross sections, Fusion Eng. and Design, 82(2007) 73.

● RA Forrest, J Kopecky, AJ Koning, Detailed analysis of (n,p) and (n,) reactions in the EAF-2007 and TALYS-generated libraries, Fusion Eng. and Design, 83(2007) 614.

● RA Forrest, J Kopecky, AJ Koning, Revisions and improvements of neutron capture cross sections for EAF-2009 and validation of TALYS calculations, UKAEA FUS 546 (March 2008).

● RA Forrest et al., Validation of EASY-2007 using integral experiments, UKAEA FUS 547 (April 2008).

● Graphical comparison of all EAF-2007 Score =1-6 reactions, corresponding TALYS calculations (if TALYS not adopted) with experimental data (J Kopecky – private information).

Actions and updates for EAF-2009Standard treatment

● Complete revision of (exp) values is in progress. 1. Threshold reactions. Several new rules shall be applied and new error factors proposed based on TALYS validations, SACS analysis and studies and comparisons against experimental data.

► If (Eth-20 MeV) < 0.1 the value has been increased to 0.1.

► If (Eth-20 MeV) < 0.2 the value of (20 - 60 MeV) is specially treated for excitation curves with dominant cross section part above 20 MeV. Further the starting energy of the last energy group (20 MeV) has been made free, in order to better cover the the shape of the excitation curve. The use of C/E (integral data) for cross section improvements is added.

► The uncertainty visual estimate shall be applied to account for the energy range of experimental data in the shape of calculated excitation curves (see next slide).

► Details for threshold reactions are described together with relevant plots in EAF-Doc-48 to be released in December 2008.

Uncertainty ranges1,2 – weak arguments 3,4,(5) – strong arguments for

Se-74(n,2n)Se-73

Final

Cro

ss s

ection (

b)

Energy (eV)

0.0E+00

1.5E-01

3.0E-01

4.5E-01

6.0E-01

7.5E-01

5.0E+06 1.6E+07 2.7E+07 3.8E+07 4.9E+07 6.0E+07

1

2

3

4

5

Uncertainty ranges - a dream situation -

Sm-150(n,2n)Sm-149

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

5.0E-01

1.0E+00

1.5E+00

2.0E+00

2.5E+00

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataBRC02LRL04

Tm-169(n,2n)Tm-168

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

5.0E-01

1.0E+00

1.5E+00

2.0E+00

2.5E+00

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataExp dataExp dataExp dataJUL74LAS75BRC81ALD72ANL87AUB73LAS75SIU89JAE93LRL72LAS77LAS75BRC02AEP89

Uncertainty rangesCombination of sources

Ba-138(n,a)Xe-135

Final g Final m Final tot

Cro

ss s

ection (

b)

Energy (eV)

0.0E+00

3.0E-03

6.0E-03

9.0E-03

1.2E-02

1.5E-02

5.0E+06 1.1E+07 1.7E+07 2.3E+07 2.8E+07 3.4E+07 4.0E+07

SystmSys20Exp dataExp dataExp dataExp dataExp dataExp dataExp dataExp dataExp dataExp dataAUW76 mGIT70 gHST88 mHST88 gBHU86AUW80 mIRK76 mIRK76 gGIT70 mKIG85KIG85 mAEP92NAG95 mRI 99RI 99 mJAE88

EXP

max SACS

TALYS predictive power

(n,a) for FinalNO Act + NO A<20

Max

cro

ss s

ectio

n (b

)

Asymmetry (s)

1E-04

1E+01

1E-03

1E-02

1E-01

1E+00

0.00 0.05 0.10 0.15 0.20 0.25

SACS Emax max 1/2x

TALYS validation

TALYS predictive power for major threshold reactions (references)

● Since EAF-2007 includes 65,565 reactions and only about 1750 are supported by experimental information, the test of predictive power with TALYS calculated data is of great importance. For validation of TALYS calculations see:

● RA Forrest, J Kopecky, Statistical analysis of cross sections, Fusion Eng. and Design, 82(2007) 73.

● RA Forrest, J Kopecky, AJ Koning, Detailed analysis of (n,p) and (n,) reactions in the EAF-2007 and TALYS-generated libraries, Fusion Eng. and Design, 83(2007) 614.

● RA Forrest, J Kopecky, AJ Koning, Revisions and improvements of neutron capture cross sections for EAF-2009 and validation of TALYS calculations, UKAEA FUS 546 (March 2008).

● J Kopecky, TALYS validation plots, private communication.

TALYS predictive power for major threshold reactions (cont.)

● Neutron emission channels: For (n,n′), (n,xn), (n,n′p), (n,n′) reactions the shape of calculated cross sections is in good agreement with the trend of experimental data and the shape of the excitation curves is considered good.

● Charge particle emission channels: ► A similar conclusion was made for (n,p), (n,d), (n,)

reactions with two specific cases to look at manually. The FWHM of (n,p) reaction in the transitional range with 0.08 < s < 0.12 and max of (n,) reaction to check with SACS analysis.

► (n,t) data are now in a good agreement.► (n,h), (n,2p) reactions are the experimental data

(especially activation measurements) probably often overestimated due to the interference of competing reactions from elemental or isotopic impurities.

SACS ½ (n,p) supported by EXFOR data

Ca-43 Ti-47

Co-59 Zn-66

Fe-58 Ni-62 Cu-65 Zn-67, Pd-102,Sn-112

Transition range

(n,) EAF-2009 (preliminary)

(n,a) for FinalScore = 0 Score > 0

Max c

ross s

ectio

n (b)

Asymmetry (s)

1E-04

1E+01

1E-03

1E-02

1E-01

1E+00

0.00 0.05 0.10 0.15 0.20 0.25

(n,a) for FinalNO Act + NO A<20

Widt

h at h

alf-m

ax X

S (e

V)

Asymmetry (s)

0E+00

1E+07

2E+07

3E+07

0.00 0.05 0.10 0.15 0.20 0.25

Ir-194m

(n,t) agreement

Al-27(n,t)Mg-25

Final

Cro

ss s

ect

ion (

b)

Energy (eV)

0.0E+00

1.5E-03

3.0E-03

4.5E-03

6.0E-03

7.5E-03

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20KOS75KOS79JUL82JUL81

S-32(n,t)P-30

Final

Cros

s sec

tion

(b)

Energy (eV)

0.0E+00

1.6E-03

3.2E-03

4.8E-03

6.4E-03

8.0E-03

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20MUA65CBR62RBZ74NAG90JUL73IRK68OTC61ARK63NAG93HAM67

Ca-40(n,t)K-38

Final

Cros

s se

ctio

n (b

)

Energy (eV)

1.0E-05

1.0E-02

1.0E-04

1.0E-03

1.0E+07 1.8E+07 2.7E+07 3.5E+07 4.3E+07 5.2E+07 6.0E+07

SystmSys20Exp dataExp dataExp dataMUA65CBR62KOS82RBZ74 gTAT68 gTUR66 gJUL73 gIRK68OTC61 gSMU79 gHAM67 g

Ni-58(n,t)Co-56

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

1.0E-04

2.0E-03

3.0E-03

4.0E-03

5.0E-03

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20LNZ93KOS79JUL76SMU78GEL04NAG89GEL06GEL07

Y-89(n,t)Sr-87m

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

1.0E-08

1.0E-02

1.0E-07

1.0E-06

1.0E-05

1.0E-04

1.0E-03

1.0E+07 1.8E+07 2.7E+07 3.5E+07 4.3E+07 5.2E+07 6.0E+07

SystmSys20Exp dataExp dataRBZ74 mJUL73 mSMU79 m

Rh-103(n,t)Ru-101

Final

Cros

s se

ctio

n (b

)

Energy (eV)

1.0E-05

1.0E-01

1.0E-04

1.0E-03

1.0E-02

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmSys20Exp dataKOS75 La-139(n,t)Ba-137

Final g Final m Final tot

Cro

ss s

ectio

n (b

)

Energy (eV)

1.0E-06

1.0E-02

1.0E-05

1.0E-04

1.0E-03

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmSys20Exp dataExp dataExp dataKGU97 mKGU02 mJUL73 mSMU79 mJAE97 mJUL90MOH86 m

Bi-209(n,t)Pb-207

Final g Final m Final tot

Cro

ss s

ectio

n (b

)

Energy (eV)

1.0E-06

1.0E-01

1.0E-05

1.0E-04

1.0E-03

1.0E-02

0.0E+00 1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20KOS79JUL90LVN04

(n,He-3) problemK-41(n,h)Cl-39

Final

Cros

s sec

tion (

b)

Energy (eV)

1.0E-05

1.0E-02

1.0E-04

1.0E-03

1.0E+07 1.8E+07 2.7E+07 3.5E+07 4.3E+07 5.2E+07 6.0E+07

SystmExp dataRBZ74JUL78ARK62

Re-187(n,h)Ta-185

Final

Cros

s sec

tion

(b)

Energy (eV)

1.0E-08

1.0E-03

1.0E-07

1.0E-06

1.0E-05

1.0E-04

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmRBZ74

Sc-45(n,h)K-43

Final

Cros

s se

ctio

n (b

)

Energy (eV)

1.0E-06

1.0E-02

1.0E-05

1.0E-04

1.0E-03

1.0E+07 1.8E+07 2.7E+07 3.5E+07 4.3E+07 5.2E+07 6.0E+07

SystmJUL74ARK63

Cu-63(n,h)Co-61

Final

Cros

s sec

tion

(b)

Energy (eV)

1.0E-06

1.0E-02

1.0E-05

1.0E-04

1.0E-03

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataRBZ74JUL78ARK62

Rh-103(n,h)Tc-101

Final

Cros

s se

ctio

n (b

)

Energy (eV)

1.0E-06

1.0E-02

1.0E-05

1.0E-04

1.0E-03

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataExp dataExp dataRBZ74DEB66IRK65PPO66ARK68ARK62

Ag-109(n,h)Rh-107

Final

Cros

s se

ctio

n (b

)

Energy (eV)

1.0E-06

1.0E-02

1.0E-05

1.0E-04

1.0E-03

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataRBZ74

In-115(n,h)Ag-113

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

1.0E-08

1.0E-02

1.0E-07

1.0E-06

1.0E-05

1.0E-04

1.0E-03

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataExp dataRBZ74

Tm-169(n,h)Ho-167

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

1.0E-08

1.0E-03

1.0E-07

1.0E-06

1.0E-05

1.0E-04

5.0E+06 1.4E+07 2.3E+07 3.3E+07 4.2E+07 5.1E+07 6.0E+07

SystmExp dataJUL78

Actions and updates for EAF-2009 (cont.) Standard treatment

► Details for threshold reactions are described together with relevant plots in EAF-Doc-48 to be released in December 2008.

2. Non-threshold reactions. Complete revision of (exp) values shall be performed again with improved rules and new error factors based on TALYS validations, SACS analysis and agreements with experimental data:

► Details will be described together with relevant plots in EAF-Doc-49 to be released by April 1, 2009.

3. Uncertainties with TALYS. The uncertainties for a limited number of important targets will be obtained by applying a Monte Carlo method to the TALYS nuclear reaction code.

Error factors (EAF-2009) – in progress * - good fit with experimental data

& - shape problems close to the threshold# - shape problem > 20 MeV for (n,p) and (max) for (n,)

Reaction Systematic Error factor (f) EH(th)<f<20MeV

(n,n) Vonach 1.5* (n,2n) Badikov 1.2* (n,3n) Estimate (exp. fit) 1.5* (n,4n) Estimate (exp. fit) 1.5* (n,n) Estimate (exp. fit) 3.0* (n,d)+(n,np) Forrest 2.0 (n,np) Kopecky 2.0 (n,t)+(n,nd) Forrest 1.6& (n,nt) Estimate 5.0 (n,nh) Estimate 5.0 (n,f) Estimate (calc) 1.5 (n,f) Estimate (syst) 3.0 (n,) Kopecky 1.5 (n,p) Forrest 1.5# (n,h) Lishan 1.9& (n,) Madjdedin 1.6# (n,2p) Estimate 3.0

TALYS Monte Carlo calculation (A. Koning)

● The uncertainties are obtained by applying a Monte Carlo method on the TALYS nuclear reaction code. In the fast neutron range, a number of model parameters (between 20 and 30) are varied. These parameters concern:► the optical model► the level density model► pre-equilibrium parameters► gamma-ray model parameters

● They are randomly varied following a normal distribution, centered at the default TALYS parameter values, with a default standard deviation. These two values (mean and standard deviation) are obtained from a global fitting procedure so that a default TALYS calculation is rather close to experimental data from F-19 to Bi-209.

TALYS Monte Carlo calculationFrom the scatter of (n,) curves after 100 runs the average,

error bars and all covariance matrix elements can be derived.

MF33 of EAF-2009 for special targetsTALYS calculations

Selection of important reactions for TALYS uncertainties

● Importance diagrams with factor > 1 (90% of activation) used to select a number of reactions for most materials includes 5105 reactions.

● Daughter nuclide Importance H1(n,g)H2 |H3 5 H2(n,g)H3 |H3 5 He3(n,p)H3 |H3 5 He4(n,2n)He3 |H3 5 Li6(n,p)He6 |He6 3 Li6(n,a)H3 |H3 5 Li7(n,na)H3 |H3 5 Li7(n,g)Li8 |Li8 5 Li7(n,d)He6 |He6 5 Be10(n,na)He6 |He6 3 Be10(n,g)Be11 |Li8, Be11 5 Be10(n,t)Li8 |Li8 3 Be10(n,nta)H3 |H3 1 Be9(n,nt)Li6 |He6 2 Be9(n,g)Be10 |H3, Li8, Be10, Be11 5 …… etc

Selection of important reactions for TALYS uncertainties

● From the previous list of important reactions a selections has been made for reactions on important targets for materials relevant to present fusion applications. This resulted in the following targets: Li6,7; Be9,10; B10,11; C12-14; N14,15; O16-18; F19, Sc45,46,48; Ti46-50; V49-51; Cr50,52-54; Mn54,55; Fe54,56-59; Co57-60; Ni58-64; Cu63,65; Nb91-95; Mo92,94-98,100; Ta177,179,180m-182; W180-186; Re185-187, Os184,186-190,192,193; Pb204-209; Bi203-209 and Po210.

● This selection amounts to 100 isotopic targets and all reaction channels shall be calculated. The calculation will be performed in 1, 2 and 5 MeV energy steps for data for energy regions <20MeV, 20-30MeV and 30-60MeV, respectively. The results will be used to overwrite the existing error factors for these reaction channels.

EAF v TALYS uncertainties

Good agreement!

Na-23(n,2n)Na-22

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

2.4E-02

4.8E-02

7.2E-02

9.6E-02

1.2E-01

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

NEG76ARK76STF69LOU73RI 99CCP72LNZ95LNZ95TOH92FUD91AEP92SAC65IBJ80LOK67RI 99JAE88GEL65

EAF v TALYS uncertainties

EAF uncertainty smaller – use of

experimental data near threshold

Na-23(n,t)Ne-21

Final

Cro

ss s

ectio

n (b

)

Energy (eV)

0.0E+00

4.0E-03

8.0E-03

1.2E-02

1.6E-02

2.0E-02

1.0E+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+07

SystmSys20LRL85

Conclusions

●A thorough revision and extension of the uncertainty data for EAF-2009 by a combination of an improvement of error-factor approach and TALYS Monte Carlo calculation will be performed. This will result in a new high-quality uncertainty file in MF33 format.

● The derivation of energy dependent error factors, based on TALYS Monte Carlo calculations, will be considered to replace the single-value (energy independent) factors f.

●Use the results of the recent TENDL-2008 library and especially the future TENDL-2009 release.