EASY-2005
activation library and
future plans
Robin Forrest
Euratom/UKAEA Fusion Association
Culham Science Centre
This work was funded jointly by the United Kingdom Engineering and Physical Sciences
Research Council and by EURATOM
Outline
 Introduction
 Need for n-induced data > 20 MeV
 Need for d-induced data
 SAFEPAQ-II
 Tool for creating activation libraries
 EAF-2005
 The new libraries
 Validation
 New tools for library analysis
 Deuteron-induced activation
 Work towards EAF-2005.1
 Future work: EAF-2007
 Conclusions
Introduction
 Understanding and predicting effect of neutrons on materials
is fundamental to fusion technology
 European Activation System (EASY) is the European tool
 Previous versions such as EASY-2003 have an energy
range < 20 MeV
 Materials test facilities (IFMIF) use accelerators, high energy
neutron tail  upper energy limit is ~55 MeV
 Need to extend EASY, has been carried out over 2 years,
EASY-2005 is current version
 IFMIF will use deuterons, there is a need for a library of
deuteron-induced cross sections that can be used as part of
EASY to enable activation studies
European Activation System (EASY)
EASY
Developer
SAFEPAQ-II
User
EAF libraries
FISPACT
User Interface
EAF Cross sections
EAF Decay data
EAF hazards, clearance, transport
SAFEPAQ-II
 Many data sources are used to assemble the EAF library
 All data stored in relational databases
 SAFEPAQ-II is the software tool that enables the databases
to be:
 Processed
 Visualised
 Validated
 Output
 Extended to treat s above 20 MeV
 Extended to treat d-induced data
New SAFEPAQ-II features
 Able to read IEAF and TALYS libraries
 New group structures with 211 and 351 energy groups
 New uncertainty group between 20 and 60 MeV
 MT numbers for summed reactions (MT >200)
 e.g. (n,a+) = (n,a) + (n,n′h) + (n,pt) + (n,n′pd) + (n,2n2p)
 Validation histograms showing (C/E) for the various reaction
classes produced for any source library
 For a library now have a choice of incoming particle (n or d)
 SAFEPAQ-II: User Manual, R.A. Forrest, UKAEA FUS 454,
Issue 6 (January 2005)
Experimental data
The use of experimental data is fundamental to SAFEPAQ-II
 Internal database principally at thermal, 30 keV, 14,5 MeV
 Complete EXFOR (2 CD-ROMs), relevant subset used for
visualisation
 Integral data, stored as ‘effective cross sections’ in specified
neutron spectra
 Another EXFOR CD-ROM containing d-induced data
produced by NEA Data Bank
The data are used for:
 Splitting cross sections into ground and isomeric
contributions
 Renormalisation
 Validation
EAF-2005 cross sections
 EAF-2005 requires data from 20 – 60 MeV
 Calculated data produced by TALYS for data > 20 MeV
 SAFEPAQ-II automatically smoothly joins TALYS-5 data at
20 MeV to existing data in EAF-2003
 For new reactions (generally with high thresholds) TALYS-5
data are used
 A set of new MT numbers agreed with A Koning, allowing up
to 8 particles to be emitted
 62,637 reactions (12,617 in EAF-2003)
 50 data sources
 86 different reaction types (23 in EAF-2003)
 The European Activation File: EAF-2005 cross section
library, R.A. Forrest, J. Kopecky and J-Ch Sublet, UKAEA
FUS 515 (January 2005)
EAF-2005 decay data
 New reactions will lead to the production of radio-nuclides
not considered in the EAF-2003 decay data library
 EAF-2005 contains 2,192 nuclides (278 new)
 The new nuclides also require data on biological hazards,
clearance and A2
 The European Activation File: EAF-2005 decay data library,
R.A. Forrest, UKAEA FUS 516 (January 2005)
 The European Activation File: EAF-2005 biological,
clearance and transport libraries, R.A. Forrest, UKAEA FUS
517 (January 2005)
New reaction types (but standard ENDF)
Reaction
MT value
 (n,2nd)
 (n,n´3a)
 (n,2n2a)
 (n,n'd2a)
 (n,n´t2a)
 (n,3np)
 (n,n´2p)
 (n,n´pa)
 (n,3a)
 (n,t2a)
 (n,d2a)
 (n,pd)
 (n,pt)
 (n,da)
11
23
30
35
36
42
44
45
109
113
114
115
116
117
New reaction types (non-standard)
Reaction
MT value
 (n,5n)
152
 (n,6n)
153
 (n,2nt)
154
 (n,ta)
155
 (n,4np)
156
 (n,3nd)
157
 (n,n´da)
158
 (n,2npa)
159
 (n,7n)
160
 (n,8n)
161
 (n,5np)
162
 (n,6np)
163
 Plus 37 further reactions
27Mg
Data for 27Al(n,p)
Al-27(n,p)Mg-27
1.5E-01
Systm
TSU88
ANL87
KTO88
KTO90
AUW00
RAS78
MUA85
TIL92
BUC92
TIL87
TIL92
USM85
RI 72
CHM86
BIA78
GEL00
JAE88
BIR76
TSU88
NPL78
KOS82
THS85
KOS86
RI 97
JAE93
BIA78
BIR85
BIR85
KOS86
LAS67
BIA83
KTY62
SHI77
HAR60
NPL72
ANL75
ANL75
NAP68
LAS54
ANL75
Cross section (b)
1.2E-01
9.0E-02
6.0E-02
3.0E-02
0.0E+00
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
Smooth join of
EAF-2003 with
TALYS-5
EAF-2005
 Builds on EAF-2004, improves quality of data
 Further extension of SAFEPAQ-II
 New differential measurements
 New integral measurements
 Use of TALYS-5 data
 Use of LEA for improvement of (n,a) and (n,p) low energy
data
 Improvement of 2 and 4 group uncertainty data
 The charged particle libraries required for SCPR all new –
based on TALYS calculations, also extended to 60 MeV
New differential and integral data
 Filatenkov has measured 14 reactions that were discrepant
 Kopecky has searched EXFOR to find all data > 20 MeV
 A new source of integral data identified:
 S. Qaim et al., KfK Jülich in late seventies
 New integral data for Y, Pb, Ta
 Use of FZK and Řež integral data > 20 MeV
TALYS-5 and -5a data
 A calculation for all targets using global parameters output in
EAF format by A Koning
 Corrects many problems identified in TALYS-4
 Better physics
 ‘Smoother’ high energy data
 Charged particle emission improved (still not perfect)
 Is default choice for > 20 MeV data
TALYS-5 improvement
– 58Ni(n,2n)57Ni
Ni-58(n,2n)Ni-57
RI 99
KHA96
KHA96
BUC92
KIG84
BHU86
SST87
KTO88
AUB82
KOS81
GEL02
ANL87
ANL87
RAM91
KOS82
RAB91
LNZ92
IBJ80
GEL02
IRK85
JAE84
IRK82
AEP89
RI 97
IRK85
IRK82
JAE88
1.0E-01
Cross section (b)
8.0E-02
6.0E-02
4.0E-02
Better fit to data
2.0E-02
Less ‘bumps’
0.0E+00
1.0E+07
2.0E+07
3.0E+07
4.0E+07
Energy (eV)
TALYS-5
TALYS-4
5.0E+07
6.0E+07
New EXFOR Fe-56(n,p)Mn-56
data – 56Fe(n,p)56Mn
2.0E-01
Systm
Sys20
NPT91
KTO88
SST87
OHO91
ANL75
AEP93
KTO90
TIL92
TIL92
RI 78
CRC64
GEL00
AEP98
LVN00
GEL00
BIR76
HAM62
ANL75
RAB91
RI 97
JAE93
MOH82
LAS58
KOS80
TSU84
JAE88
LAS67
LAS58
CRC64
GEL66
ANL75
NPT91
AEP89
AEP89
CRC64
Cross section (b)
1.6E-01
1.2E-01
8.0E-02
4.0E-02
0.0E+00
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
EXFOR data
> 20 MeV
New EXFORCo-59(n,3n)Co-57
data - 59Co(n,3n)57Co
1.2E+00
JUL80
TOH96
LAS77
TOH99
Cross section (b)
9.6E-01
TALYS-5 in very
good agreement
with new high
energy data
7.2E-01
Significant
improvement
over EAF-2004
4.8E-01
2.4E-01
0.0E+00
1.0E+07
1.8E+07
2.7E+07
3.5E+07
4.3E+07
Energy (eV)
Final
TALYS-5
IEAF-2001
MENDL-2
5.2E+07
6.0E+07
Low Energy Approximation (LEA)
 Represents the region below the effective threshold of (n,p)
and (n,a) reactions with Q > 0 by resonance data and or
pure 1/v (if no resonances exist)
 Based on assumption that R = s(p)/s(g) or s(a)/s(g) is
constant at low energies
Pd-107 s(a)/s(g)
R
Ag-107 s(p)/s(g)
En (keV)
36Cl
K-39(n,a)Cl-36
LEA for 39K(n,a)
1.0E+00
1.0E-01
Cross section (b)
1.0E-02
Systm
Sys20
IFJ65
NZW67
HAM60
HAM58
OTC61
FRK64
HAM62
RIC61
EAF-2005
1.0E-03
1.0E-04
1.0E-05
1.0E-06
EAF-2003
1.0E-07
1.0E-08
1.0E-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+076.0E+07
Energy (eV)
Final
EAF-2003.0
Se-80(n,p)As-80
New differential
data – 80Se(n,p)80As
4.0E-02
EAF-2005 based on
TALYS-5
renormalised to
Filatenkov data
Systm
Sys20
TUR67
KRI04
Cross section (b)
3.2E-02
2.4E-02
EAF-2003 based on
JEF-2.2
1.6E-02
8.0E-03
0.0E+00
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
EAF-2003.0
4.0E+07
5.0E+07
6.0E+07
Nb-93(n,a)Y-90m
Integral dataNb-93(n,a)Y-90m
– 93Nb(n,a)90mY
Systm
Sys20
SEO86 m
IRK83
KIG85 m
AUB82 m
ORL58 g
AUB79 m
NPL81 m
AEP89 m
CIP85 m
BUC92 m
DEB98 m
RI 01 m
RI 01 g
GEL00 m
GEL00 m
RAM91 m
AEP77 m
JAE88 m
IBJ75 m
LAS61
JUL88
JUL88 m
LRL60
GEL87 m
GEL87 m
GEL88
RI 97 m
GEL88 m
7.5E-03
7.5E-03
Cross section (b)
6.0E-03
6.0E-03
4.5E-03
4.5E-03
3.0E-03
3.0E-03
1.5E-03
1.5E-03
0.0E+00
0.0E+00
0.0E+00
0.0E+00
1.0E+07
1.0E+07
2.0E+07
2.0E+07
3.0E+07
3.0E+07
4.0E+07
4.0E+07
Energy
Energy(eV)
(eV)
Final
Final
EAF-2003.0
EAF-2003.0
5.0E+07
6.0E+07
5.0E+07
6.0E+07
Experimental data
EAF-2003
EAF-2005
Integral C/E
improved
EAF-2003
1.0518, 1.1279
EAF-2005
1.0010, 1.0704
Validation of EASY-2005
 This is part of the current work
 Details given in talk by Jura Kopecky
 Work so far has identified some problems with EAF-2005
 Validation report will be produced at end of 2005
 Currently there are 448 reaction studied, of these 208 are
validated
 Based on C/E plots of integral data and plots of differential
data as a function of energy
New SAFEPAQ-II tools
 Verification and validation of very large EAF-2005 library is
difficult – need for additional tools
 Systematics show that cross sections at particular energies
have a good correlation with parameters such as A or
s = (N - Z) / A
 Work on maximum cross sections by Manokhin for (n,2n)
shows similar trend
 SAFEPAQ-II can extract such data from EAF-2005 or one of
the data sources (such as TALYS-5) and display a scatter
plot against A, Z or s
 Line of best fit can be added and reactions discrepant from
the trend identified
Cross section analysis
Data source
x-axis variable
Reaction
Nonthreshold
reactions
need to
specify a
minimum
energy
y-axis variable
Option to add a 2nd reaction e.g.
(n,2n) + (n,n′p)
Plot
Maximum cross section
(n,2n)
(n,2n)-for
Final for EAF-2005
1E+01
Max cross section (b)
Trend
1E+00
Nb-91m(n,2n), what is wrong?
1E-01
1E-02
Hf-178n(n,2n), what is wrong?
1E-03
0
50
100
150
200
Atomic Mass (A)
Even Z,Even N
Even,Odd
Odd Z,Odd N
250
300
178Hf(n,2n)
2.5E+00
178mHf(n,2n)
and
Hf-178(n,2n)Hf-177
Hf-178(n,2n) data from
TALYS-5a, but no data for
the high spin Hf-178n isomer
in TALYS-5a
Systm
Cross section (b)
2.0E+00
Use ADL-3, no
renormalisation to
systematics and data very
small
1.5E+00
1.0E+00
Need to improve
5.0E-01
0.0E+00
5.0E+06
1.4E+07
2.3E+07
3.3E+07
Energy (eV)
TALYS-5a
4.2E+07
5.1E+07
6.0E+07
91mNb(n,2n)
90gNb
Nb-91m(n,2n)Nb-90g
3.0E+00
Systm
Cross section (b)
2.4E+00
Error with first point in
TALYS-5, should be 0
1.8E+00
Need to improve
1.2E+00
6.0E-01
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
Width at half-maximum - (n,2n) for EAF-2005
(n,2n) for Final
Width at half-max XS (eV)
6E+07
5E+07
4E+07
Kr-76(n,2n), what is wrong?
3E+07
2E+07
1E+07
0E+00
0
50
100
150
Atomic Mass (A)
200
250
300
76Kr(n,2n)75Kr
Kr-76(n,2n)Kr-75
7.5E-02
Large width is due to
shape of TALYS-5 data,
need to improve?
Cross section (b)
6.0E-02
4.5E-02
3.0E-02
1.5E-02
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
Deuteron-induced data
 IFMIF uses high energy d beams on a flowing lithium target
 Corrosion products in the lithium means that reactions of d
with a wide range of elements possible
 Need to be able to calculate the d-induced activation
 A d library (based on TALYS calculations) is being
constructed, FISPACT will be modified so that the data can
be used
 The range of targets and reactions is similar to EAF-2005:
 60,688 reactions
 2,192 nuclides
 Based on calculated data from TALYS
 Very limited use of experimental data
58Ni(d,na)55Co
Ni-58(d,na)Co-55
5.0E-02
PUP63
ROC63
Cross section (b)
4.0E-02
Good agreement of
EXFOR with TALYS
calculation
3.0E-02
2.0E-02
1.0E-02
0.0E+00
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
63Cu(d,2n)63Zn
Cu-63(d,2n)Zn-63
2.5E-01
OSA71
BLG63
Cross section (b)
2.0E-01
Good agreement of
EXFOR with TALYS
calculation
1.5E-01
1.0E-01
5.0E-02
0.0E+00
5.0E+06
1.4E+07
2.3E+07
3.3E+07
Energy (eV)
Final
4.2E+07
5.1E+07
6.0E+07
51V(d,2n)51Cr
V-51(d,2n)Cr-51
1.0E+00
CIN93
AEP92
JUL80
Very poor
agreement of
EXFOR with TALYS
calculation.
Cross section (b)
8.0E-01
6.0E-01
More work needed!
4.0E-01
2.0E-01
0.0E+00
0.0E+00
1.0E+07
2.0E+07
3.0E+07
Energy (eV)
Final
4.0E+07
5.0E+07
6.0E+07
FISPACT-2005
 Inventory code - calculates arisings of nuclides following
neutron exposure
 Developed over last 19 years for fusion applications
 Features
 External libraries of cross section and decay data
 Elements hydrogen to fermium handled
 Arbitrary irradiations (multiple pulses)
 Arbitrary neutron spectrum
 Gas production and isomers
 Sensitivity and uncertainty calculations
 Dominant nuclides and pathways
 Fissionable actinides
 Sequential charged particle reactions
 Test version has ability to read a d-induced library
EASY-2005.1
 Obvious errors in the cross sections described above will
be corrected
 Implement ability to read d-induced library in FISPACT
 Bug fixes in User Interface
 Maintenance release at end of 2005
 Feedback from validation studies and physics
improvements will be collected and implemented in the
next version
 Validation report for EASY-2005 distributed at end of 2005
EASY-2007
 EAF-2007
 implement feedback from integral validation
 New TALYS-6 results
 Will contain more complete d-induced library
 Use detailed calculations on selected elements (Avrigeanu)
 Use of EXFOR data or branching and renormalisation
 Uncertainties?
 Documentation
Activation handbook
 Example of use of EAF-2003 data
 All elements irradiated in fusion relevant neutron spectra
 544 pages of tabular and graphical data
 Importance diagrams are spectrum independent
 Results without running an inventory code
 Handbook of Activation Data Calculated Using EASY-2003
M.R. Gilbert and R.A. Forrest, UKAEA report UKAEA FUS
509 (July 2004). (PDF file, size 8.6Mb)
 Available for download
Conclusions
 EAF-2005 completed and distributed to users
 Validation and verification during 2005
 New SAFEPAQ-II tools to help in verification
 Need for maintenance version (EAF-2005.1) to correct
errors and implement d-induced activation
 Validation and feedback to be used for EAF-2007
All EASY-2005 documentation, Validation
reports and the Activation handbook can
be downloaded from the web at
http://www.fusion.org.uk/easy2005