Task 9.4 Processing JEFF-3.2 and TENDL-2013 Neutron Files Using the NJOY-2012 and PREPRO-2010

Task 9.4 Processing JEFF-3.2 and TENDL-2013 neutron files using the NJOY-2012 and PREPRO-2010 codes

SEVENTH FRAMEWORK PROGRAMME OF THE
EUROPEAN ATOMIC ENERGY COMMUNITY
Nuclear Fission and Radiation Protection

Project acronym: CHANDA
Project full title: Solving Challenges in Nuclear Data for the Safety of
European Nuclear Facilities
Grant Agreement no.:FP7 – 605203
Workpackage N°:9
Identification N°:
Type of document:Non-contractual report
Title:
UPM contribution to Task 9.4
“Processing of nuclear data”
Processing JEFF-3.2 and TENDL-2013 neutron files
using the NJOY-2012 and PREPRO-2010 codes
Dissemination Level:PP
Reference:
Status:VERSION 0
Name / Partner / Date / Signature
written by: / O. Cabellos / UPM
Task leader / J.Ch. Sublet / CCFE / Dec. 2016
WP leader: / A.J. Koning / NRG
IP Co-ordinator:

Content

Introduction: Report contents

1.Processing Neutron Cross Section Libraries with the NJOY code

1.1.Processing ENDF libraries into HENDF format

1.2.NJOY inputs to process cross-sections

1.3.NJOY step by step

1.4.HEATR calculation

1.5.THERMR calculation

1.6.BOXER processing

2.Corrections in NJOY-2012.8

3.Covariance Processing

3.1.Processing JEFF-3.2 in BOXER format

3.2.Processing TENDL-2013 in BOXER format

3.3.Cross-correlation problem in TENDL-2013

4.References

ANNEX I

Introduction: Report contents

This report describes the processing of the evaluated nuclear data libraries JEFF-3.2 and TENDL-2013. The processing is performed with NJOY-2012 and PREPRO-2010 codes.[NEA/JEFF-3.1.2], [NEA/JANIS-2014]

For the processing with NJOY-2010.8 [NJOY-2012_up8], the following NJOY modules are used: moder, reconr, broadr, heatr, gaspr, errorr and covr.

The processed data contains kinematic kerma factors, total damage energy production and gas production cross section whenever such data are contained in the ENDF library.

A general tolerance value for the reconstruction, thinning and broadening of 0.5% is used. Broadening temperature at 293.15K.

Processing covariance data into error and boxer formats has been done using LANL-187 group structure. Some NJOY’s patches are suggested, mostly solving problems in TENDL libraries updating dimension in variables for COVER and ERROR modules.

Additionally, a quality and assurance work is performed, reporting warnings and error messages, with a visual and cross-checking of NJOY-2012 and PREPRO-2010 reconstructed cross-sections.

Warnings and errors in the processing of ENDF libraries are reported, including the main cause of the problem.

In some cases, problems in MODER/RECONR modules for PENDF processing are reported. PREPRO-2010 is used [PREPRO_2010] to process these files (Bk250, Sb124, Cs137, Fm250, Fm252, Fm253, Fm254, Fm255, Fm256, Fm257, Lr261, Lr262, Md255, Md256, Md257, Md258, Md259, Md260, Np237, Pu237, Ce143, Pa228, Tm162, Ta174, Fe058, Th233 in TENDL2010; Be-7, Ac230, Au189m, Er155 and Pa234 in TENDL 2013).

Finally, the problem with cross-correlation processing in TENDL2013 is also reported.

1.Processing Neutron Cross Section Libraries with the NJOY code

The objective of this work is the processing of the recent JEFF-3.2 and TENDL-2013 neutron files using the NJOY-2012 and PREPRO-2010 codes.

Table 1.General Purpose neutron cross sections libraries processed

ENDF Library / Isotopes/Elements
JEFF-3.2 / 472
TENDL-2013 / 2630

The processing code system to be used is NJOY-2012 [NJOY-2012_up8] and PREPRO-2010 [PREPRO-2010].

The PENDF neutron libraries are processed at 293.15 degrees Kelvin.

The processed data also contains gas production data whenever such data are contained in ENDF. Kinematic KERMA factors and total damage energy production data are processed.

The nuclides to be processed are all those of the General Purpose Library, including important light nuclei, the structural materials, the fission products, control rod materials and burnable poisons, all major and minor actinides.

For each material three files were given:

-HENDF (hybrid HENDF files including reconstructed MF3/MT3 section for consistency with MF33/MT3 PENDF cross section data)

-INTER (Output file of INTER code, version 8.02 -2012/05/16)

-BOXER and ERRORR (Covariance matrices)

1.1.Processing ENDF libraries into HENDF format

NJOY is a modular computer code used for converting evaluated nuclear data in the ENDF format into different type of libraries useful for applications calculations. The processing sequence for generating HENDF formatted library suitable for use by the JANIS program is shown below, in Fig. 1 and Fig. 2.

Figure 1.NJOY processing sequence for HENDF format

Finally, INTER code is used to calculate: thermal cross sections, g-factors, resonance integrals, fission spectrum averaged cross sections and 14.0 MeV cross sections for major reactions (Total, Elastic,(n,2n), (n,3n), Fission, (n,gamma), (n,p), (n,d), (n,t), (n,He3) and (n,alpha) ).

Figure 2.Flowchart of HENDF processing database from ENDF tapes

1.2.NJOY inputs to process cross-sections

The NJOY processing system is a modular computer code used for processing ENDF. Each module performs a well-defined processing task. These modules are linked by input and output files (tapes).

A reference input file for each material has been written and at a specific temperature of 293.15K. An example of NJOY input is given in Fig. 3. The complete set of inputs is available through NEA Data Bank.

Figure 3.Sample input data of Ac225 (MAT=8925) to generate HENDF file

1.3.NJOY step by step

HENDF format is processed following the specifications given in NJOY code. We present a summary of the most important processing options used by NJOY in a typical input file (Ac-225).

MODER

Convert ENDF “tapes” back and forth between formatted (that is, ASCII, EBCDIC, etc.) and blocked binary modes.

Input unit: 20 (tape20, ENDF cross section library)
Output unit:21

MODER reads the ENDF file (tape20) which contains the material (for Ac-225 the material number is 8925), extract it and put the ENDF file in binary mode in tape21.

RECONR

Reconstruct pointwise (energy-dependent) cross sections from ENDF resonance parameters and interpolation schemes.

Reconstruction tolerance (ERR): 0.5%
Resonance-integral-check tolerance (ERRINT): 0.5%
Reconstruction temperature: 0.0 K

RECONR read tape21, extract material 8925 and reconstruct cross section at 0K with a reconstruction tolerance of 0.5%. The resulting pointwise cross section is written in tape22.

BROADR

Doppler-broadens and thins pointwise cross sections.

Thinning tolerance: 0.5%
Integral criterion tolerance:0.5%
Maximum energy: Doppler broadening was force up to the upper energy limit of the resolve resonance range, but never above 10.0 MeV
Temperature: 293.15 K

BROADR reads tape21-tape22 and Doppler-broadens at 293.6K for material 8925.The tolerance used is 0.5%. The results are written in tape23.

GASPR

Add gas production (mt203-207) to PENDF.

GASPR add gas production reactions to PENDF tape23. Output file is tape24

THERMR

Produce cross sections and energy-to-energy matrices for free or bound scatters in the thermal energy range.

Number of angles bins: 12
Tolerance:0.5%
Max. energy:5 eV
Scattering option: 221 (free gas)
Temperature:293.15 K

THERMR generates neutron scattering cross sections and point-to-point scattering kernels in the thermal range. The input file is only tape24, the output file is tape25. The generation of neutron scattering cross sections is doing for material 8925 with 12 equi-probable angles at 293.15K. Free gas option is chosen and no elastic cross sections in the thermal range. A tolerance of 0.5% and the maximum energy for thermal treatment is 5 eV.

HEATR

Generate pointwise heat production cross sections (KERMA factors) and radiation-damage-production cross sections.

MT=443: Total kinematic kerma
MT=444: Total damage energy production

HEATR computes energy-balance heating and damage energy for material 8925 at 293.15 K. Input files are tape21-tape23. The output file is tape24.

1.4.HEATR calculation

The HEATR module generates pointwise heat production cross sections and radiation damage energy production for specified reactions and adds them to an existing PENDF tape.

By default, the code processes the energy-balance total KERMA (MT=301) only. In this work, we have included MT443 and MT444 also.

NJOY computes the kij(E) factors (KERMA, Kinetic Energy Release in Materials) for material-i and reaction-j at incident energy E. The units are eV-barns.

Using the energy-balance method NJOY computes kij(E) as follows:

where:

Qij is the mass-difference Q value for material-i and reaction-j

is the total energy of secondary neutrons including multiplicity

is the energy of secondary photons including photon yields

The kinematic KERMA computed when MT443 is requested is very useful for judging the energy-balance consistency of an evaluation. It can also be used instead of the energy-balance value in MT301 when local heating effects are important and the evaluation scores poorly in an energy-balance check.

Damage energy production cross sections (MT444) is interested for important structural materials; this calculation can be omitted for other materials. The Damage output from HEATR is the damage energy production cross section (eV-barns). So, we define as the energy available to cause displacements.

Table 3.Special NJOY’s labels are included in HENDF format (from Table XV-7, NJOY manual)

Name / MT / Description
HEAT / 301 / Energy-balance heat production
KERMA / 443 / Kinematic KERMA factor
DAMAGE / 444 / Damage-energy production

1.5.THERMR calculation

The THERMR module generates pointwise neutron scattering cross section in the thermal range.

The PENDF tape contains static cross section and cross sections for several different binding states:

-MT=2 for static

-MT=221 for free gas model (Inelastic scattering in thermal energy range)

1.6.BOXER processing

In addition, NJOY is used to predict covariance matrices using ERRORR and COVR modules. Fig.4 shows the processing sequence and Fig.5 shows the input for Ac225.

Figure 4.NJOY processing sequence for BOXER format

Figure 5.Sample input data of Ac225 (MAT=8925) to generate HENDF formatted library in BOXER format

moder /tape20 from MERGER
20 21
reconr /Reconstruct XS data
21 22
' PENDF tape ' /
8925 2/
.005 0. 0.005/
' MAT=ac225 ENDF Library: JEFF-3.2 ' /
' Processed by NJOY2012,NEA Data Bank,2014'/
0/
broadr /Doppler broaden XS
21 22 23
8925 1 0 0 0.
.005 2.0e+6 0.005/
293.15
0/
errorr
21 23 0 77 /
8925 10 2 1 1 /
1 293.15 /
0 33 /
covr
77 78/
3 1
' Processing Covariances ' /
' in BOXER format ' /
8925 0 0 0 /
stop

In this work, MF32 and MF33 are processes in LANL-187 group energy structure using constant flux.

ERRORR

It computes multigroup covariance matrices from ENDF uncertainties.

IGN: 10 (lanl 187-group structure)
IWT: 2 (constant)
Temperature: 293.15 K

2.Corrections in NJOY-2012.8

The initial version used to process this library is NJOY-2012.8 taken from Official Updates (LANL) in:

In this work some NJOY patches are proposed named as: “NEA DB/Jun2014 updates”.

1) In COVR, the "deallocate(y)" is repeated twice.

...
...
call press(0,nout,cf,2,ixmax)
190 continue
deallocate(x)
!!deallocate(y) ! NEA DB, June2014
if (allocated(rsdx)) deallocate(rsdx)
...
...

2) In ERRORR, subroutine "grpav.f", increasing the size in "scr" vector.

...
...
if ((npage+50).gt.nwds) nwds=npage+50
!!allocate(scr(nwds))! NEA DB, June2014
allocate(scr(nwds+500))
nsigz=1
...
...

3) In ERRORR, subroutine "egngpn.f" where no allocate is done for ign16-17, and the same problem is found for ign=18.

...
...
!--vitamin-e 174- and vitamin-j 175-group structures (ornl-5510)
else if (ign.eq.16.or.ign.eq.17) then
ngn=174
ngp=ngn+1 ! NEA DB, June2014
if (ign.eq.17) ngp=176 ! NEA DB, June2014
allocate(egn(ngp)) ! NEA DB, June2014
do ig=1,175
egn(ig)=gl15(ig)
enddo
...
...

4) In ERRORR, increasing dimensions of “mxlru2”

...
...
subroutine resprx(nwscr,a)
!------
! prepare tables containing the resonance-parameter contributions
! to coarse-group covariances.
!------
useendf ! provides endf routines and variables
useutil ! provides error,openz,repoz,closz
usesamm ! provides desammy
usemainio ! provides nsyso
! externals
integer::nwscr
real(kr)::a(nwscr)
! internals
integer::indx
integer::nb,nw,nngn,ig,ner
integer::ip1,ip2,i,iest,ieed,iscr,jscr,nro,mls
!!integer,parameter::mxlru2=100 ! NEA DB, June2014
integer,parameter::mxlru2=10000
...
...

5) In ERRORR, increasing dimensions of “mxnpar”.

...
...
subroutine rpxlc12(nwscr,a,iest,ieed)
!------
! Resolved resonances: lru=1, lcomp=1 or 2
!------
usemainio ! provides nsyso
useendf ! provides endf routines and variables
use physics ! provides amassn
useutil ! provides error,mess
! externals
integer::nwscr,iest,ieed
real(kr)::a(nwscr)
! internals
integer::nb,nw,lru1,lrf1,lb,i,ig,ig2,il,ii2,ii1,ipp,j
integer::loopm,loopn,loop,ns,nrs1,nsmax,ipos,l1,l2,l3
integer::lb2,lldum,igind,ipara,itmp,ilnum,ind,ii
integer::imess,inow,jj,lll,nrs
integer,parameter::maxe=600000
!!integer,parameter::mxnpar=7000 ! NEA, Jun2014
integer,parameter::mxnpar=9000
...
...

6) In ERRORR, change the position of line “integer::nmtres,ncoef,nresp,ier”

...
...
subroutine cssammy(e,sigp,siga,sigd,mmtres,nmtres,ncoef,nresp,ier)
!------
! Calculates RM or RML cross sections at energy e
! for one section using the SAMMY method.
!------
usemainio ! provides nsyso
! externals
integer::nmtres,ncoef,nresp,ier ! NEA, Jun2014
real(kr)::e,sigp(nmtres+2),siga(ncoef,nmtres),sigd(nresp,nmtres)
integer::mmtres(10)
!!integer::nmtres,ncoef,nresp,ier ! NEA, Jun2014
...
...

3.Covariance Processing

In this section, the verification of warnings and error messages is assessed in the processing. Cross-checking of NJOY2012 and PREPRO2010 will permit to solve some cases where NJOY-2012 crashed.

3.1.Processing JEFF-3.2 in BOXER format

JEFF-3.2 has been processed using ERRORR/COVR NJOY modules. Table 4 shows the covariance data included in JEFF-3.2 to be processed.

Table 4. List of 201 isotopes/materials with covariance data in JEFF-3.2, and processed with NJOY2012.8.

MAT / Isotope / MF31 / MF32 / MF33 / MF34 / MF35 / MF40
125 / 1-H-001 / - / - / YES / - / - / -
325 / 3-Li-006 / - / - / YES / - / - / -
525 / 5-B-010 / - / - / YES / - / - / -
528 / 5-B-011 / - / - / YES / - / - / -
600 / 6-C-000 / - / - / YES / - / - / -
628 / 6-C-013 / - / YES / YES / YES / - / -
728 / 7-N-015 / - / - / YES / - / - / -
828 / 8-O-017 / - / YES / YES / YES / - / -
831 / 8-O-018 / - / YES / YES / YES / - / -
925 / 9-F-019 / - / - / YES / - / - / -
1025 / 10-Ne-020 / - / YES / YES / YES / - / -
1028 / 10-Ne-021 / - / YES / YES / YES / - / -
1031 / 10-Ne-022 / - / YES / YES / YES / - / -
1125 / 11-Na-023 / - / - / YES / - / - / -
1234 / 12-Mg-027 / - / YES / YES / YES / - / -
1425 / 14-Si-028 / - / - / YES / - / - / -
1428 / 14-Si-029 / - / - / YES / - / - / -
1431 / 14-Si-030 / - / - / YES / - / - / -
1434 / 14-Si-031 / - / YES / YES / YES / - / -
1437 / 14-Si-032 / - / YES / YES / YES / - / -
1525 / 15-P-031 / - / YES / YES / YES / - / YES
1625 / 16-S-032 / - / YES / YES / YES / - / -
1628 / 16-S-033 / - / YES / YES / YES / - / -
1631 / 16-S-034 / - / YES / YES / YES / - / -
1637 / 16-S-036 / - / YES / YES / YES / - / -
1728 / 17-Cl-036 / - / YES / YES / YES / - / YES
1834 / 18-Ar-039 / - / YES / YES / YES / - / YES
1840 / 18-Ar-041 / - / YES / YES / YES / - / YES
1925 / 19-K-039 / - / YES / YES / YES / - / YES
1928 / 19-K-040 / - / YES / YES / YES / - / YES
1931 / 19-K-041 / - / YES / YES / YES / - / YES
2028 / 20-Ca-041 / - / YES / YES / YES / - / YES
2040 / 20-Ca-045 / - / YES / YES / YES / - / -
2128 / 21-Sc-046 / - / YES / YES / YES / - / YES
2225 / 22-Ti-046 / - / - / YES / - / - / -
2228 / 22-Ti-047 / - / - / YES / - / - / -
2231 / 22-Ti-048 / - / - / YES / - / - / -
2234 / 22-Ti-049 / - / - / YES / - / - / -
2237 / 22-Ti-050 / - / - / YES / - / - / -
2300 / 23-V-000 / - / - / YES / - / - / -
2322 / 23-V-049 / - / YES / YES / YES / - / YES
2425 / 24-Cr-050 / - / YES / YES / - / - / YES
2428 / 24-Cr-051 / - / YES / YES / YES / - / YES
2431 / 24-Cr-052 / - / YES / YES / - / - / -
2434 / 24-Cr-053 / - / YES / YES / - / - / YES
2437 / 24-Cr-054 / - / YES / YES / - / - / YES
2519 / 25-Mn-053 / - / YES / YES / YES / - / YES
2522 / 25-Mn-054 / - / YES / YES / YES / - / YES
2525 / 25-Mn-055 / - / YES / YES / YES / - / -
2625 / 26-Fe-054 / - / - / YES / - / - / -
2631 / 26-Fe-056 / - / - / YES / YES / - / -
2634 / 26-Fe-057 / - / - / YES / - / - / -
2637 / 26-Fe-058 / - / - / YES / - / - / -
2719 / 27-Co-057 / - / YES / YES / YES / - / YES
2725 / 27-Co-059 / - / - / YES / - / - / -
2728 / 27-Co-060 / - / YES / YES / YES / - / YES
2825 / 28-Ni-058 / - / - / YES / YES / - / -
2831 / 28-Ni-060 / - / - / YES / YES / - / -
2834 / 28-Ni-061 / - / - / YES / - / - / -
2837 / 28-Ni-062 / - / - / YES / - / - / -
2840 / 28-Ni-063 / - / YES / YES / YES / - / YES
2843 / 28-Ni-064 / - / - / YES / - / - / -
2928 / 29-Cu-064 / - / YES / YES / YES / - / YES
2934 / 29-Cu-066 / - / YES / YES / YES / - / YES
3025 / 30-Zn-064 / - / YES / YES / YES / - / YES
3031 / 30-Zn-066 / - / YES / YES / YES / - / YES
3034 / 30-Zn-067 / - / YES / YES / YES / - / YES
3037 / 30-Zn-068 / - / YES / YES / YES / - / YES
3043 / 30-Zn-070 / - / YES / YES / YES / - / YES
3225 / 32-Ge-070 / - / YES / YES / YES / - / -
3231 / 32-Ge-072 / - / YES / YES / YES / - / YES
3234 / 32-Ge-073 / - / YES / YES / YES / - / YES
3237 / 32-Ge-074 / - / YES / YES / YES / - / YES
3243 / 32-Ge-076 / - / YES / YES / YES / - / YES
3325 / 33-As-075 / - / YES / YES / YES / - / YES
3425 / 34-Se-074 / - / YES / YES / YES / - / YES
3431 / 34-Se-076 / - / YES / YES / YES / - / YES
3434 / 34-Se-077 / - / YES / YES / YES / - / YES
3437 / 34-Se-078 / - / YES / YES / YES / - / YES
3440 / 34-Se-079 / - / YES / YES / YES / - / YES
3443 / 34-Se-080 / - / YES / YES / YES / - / YES
3449 / 34-Se-082 / - / YES / YES / YES / - / YES
3525 / 35-Br-079 / - / YES / YES / YES / - / YES
3531 / 35-Br-081 / - / YES / YES / YES / - / YES
3625 / 36-Kr-078 / - / YES / YES / YES / - / YES
3631 / 36-Kr-080 / - / YES / YES / YES / - / YES
3637 / 36-Kr-082 / - / YES / YES / YES / - / YES
3649 / 36-Kr-086 / - / YES / YES / YES / - / YES
3725 / 37-Rb-085 / - / YES / YES / YES / - / YES
3728 / 37-Rb-086 / - / YES / YES / YES / - / YES
3734 / 37-Rb-088 / - / YES / YES / YES / - / YES
3825 / 38-Sr-084 / - / YES / YES / YES / - / YES
3831 / 38-Sr-086 / - / YES / YES / YES / - / YES
3834 / 38-Sr-087 / - / YES / YES / YES / - / YES
3837 / 38-Sr-088 / - / YES / YES / YES / - / YES
3840 / 38-Sr-089 / - / YES / YES / YES / - / YES
3843 / 38-Sr-090 / - / YES / YES / YES / - / YES
3925 / 39-Y-089 / - / - / YES / - / - / -
3928 / 39-Y-090 / - / YES / YES / YES / - / YES
3931 / 39-Y-091 / - / YES / YES / YES / - / YES
4025 / 40-Zr-090 / - / YES / YES / YES / - / YES
4031 / 40-Zr-092 / - / YES / YES / YES / - / YES
4037 / 40-Zr-094 / - / YES / YES / YES / - / YES
4322 / 43-Tc-098 / - / YES / YES / YES / - / YES
4834 / 48-Cd-109 / - / YES / YES / YES / - / YES
5055 / 50-S122 / - / YES / YES / YES / - / YES
5061 / 50-S124 / - / YES / YES / YES / - / YES
5231 / 52-Te-122 / - / YES / YES / YES / - / YES
5237 / 52-Te-124 / - / YES / YES / YES / - / YES
5259 / 52-Te-131M / - / YES / YES / YES / - / YES
5322 / 53-I-126 / - / YES / YES / YES / - / YES
5328 / 53-I-128 / - / YES / YES / YES / - / YES
5634 / 56-Ba-133 / - / YES / YES / YES / - / YES
5652 / 56-Ba-139 / - / YES / YES / YES / - / YES
5825 / 58-Ce-136 / - / YES / YES / YES / - / YES
5831 / 58-Ce-138 / - / YES / YES / YES / - / YES
5834 / 58-Ce-139 / - / YES / YES / YES / - / YES
5846 / 58-Ce-143 / - / YES / YES / YES / - / YES
6329 / 63-Eu-152M / - / YES / YES / YES / - / YES
6413 / 64-Gd-148 / - / YES / YES / YES / - / YES
6428 / 64-Gd-153 / - / YES / YES / YES / - / YES
6452 / 64-Gd-161 / - / YES / YES / YES / - / -
6528 / 65-Tb-160 / - / YES / YES / YES / - / YES
6625 / 66-Dy-156 / - / YES / YES / YES / - / -
6631 / 66-Dy-158 / - / YES / YES / YES / - / YES
6637 / 66-Dy-160 / - / YES / YES / YES / - / YES
6652 / 66-Dy-165 / - / YES / YES / YES / - / YES
6729 / 67-Ho-166M / - / YES / YES / YES / - / YES
6837 / 68-Er-166 / - / YES / YES / YES / - / YES
6840 / 68-Er-167 / - / YES / YES / YES / - / YES
6843 / 68-Er-168 / - / YES / YES / YES / - / YES
6846 / 68-Er-169 / - / YES / YES / YES / - / YES
6849 / 68-Er-170 / - / YES / YES / YES / - / YES
6852 / 68-Er-171 / - / YES / YES / YES / - / YES
6855 / 68-Er-172 / - / YES / YES / YES / - / YES
6925 / 69-Tm-169 / - / YES / YES / YES / - / YES
6928 / 69-Tm-170 / - / YES / YES / YES / - / YES
6931 / 69-Tm-171 / - / YES / YES / YES / - / YES
7025 / 70-Yb-168 / - / YES / YES / YES / - / YES
7028 / 70-Yb-169 / - / YES / YES / YES / - / YES
7031 / 70-Yb-170 / - / YES / YES / YES / - / YES
7034 / 70-Yb-171 / - / YES / YES / YES / - / YES
7037 / 70-Yb-172 / - / YES / YES / YES / - / YES
7040 / 70-Yb-173 / - / YES / YES / YES / - / YES
7043 / 70-Yb-174 / - / YES / YES / YES / - / YES
7049 / 70-Yb-176 / - / YES / YES / YES / - / YES
7125 / 71-Lu-175 / - / YES / YES / YES / - / YES
7128 / 71-Lu-176 / - / YES / YES / YES / - / YES
7131 / 71-Lu-177 / - / YES / YES / YES / - / YES
7246 / 72-Hf-181 / - / YES / YES / YES / - / YES
7431 / 74-W-182 / - / - / YES / - / - / -
7434 / 74-W-183 / - / - / YES / - / - / -
7437 / 74-W-184 / - / - / YES / - / - / -
7443 / 74-W-186 / - / - / YES / - / - / -
7525 / 75-Re-185 / - / YES / YES / YES / - / YES
7531 / 75-Re-187 / - / YES / YES / YES / - / YES
7534 / 75-Re-188 / - / YES / YES / YES / - / YES
7625 / 76-Os-184 / - / YES / YES / YES / - / YES
7631 / 76-Os-186 / - / YES / YES / YES / - / YES
7634 / 76-Os-187 / - / YES / YES / YES / - / YES
7637 / 76-Os-188 / - / YES / YES / YES / - / YES
7640 / 76-Os-189 / - / YES / YES / YES / - / YES
7643 / 76-Os-190 / - / YES / YES / YES / - / YES
7646 / 76-Os-191 / - / YES / YES / YES / - / YES
7649 / 76-Os-192 / - / YES / YES / YES / - / YES
7652 / 76-Os-193 / - / YES / YES / YES / - / YES
7725 / 77-Ir-191 / - / - / YES / - / - / -
7728 / 77-Ir-192 / - / YES / YES / YES / - / YES
7825 / 78-Pt-190 / - / YES / YES / YES / - / -
7831 / 78-Pt-192 / - / YES / YES / YES / - / YES
7837 / 78-Pt-194 / - / YES / YES / YES / - / YES
7840 / 78-Pt-195 / - / YES / YES / YES / - / YES
7843 / 78-Pt-196 / - / YES / YES / YES / - / YES
7849 / 78-Pt-198 / - / YES / YES / YES / - / YES
7925 / 79-Au-197 / - / YES / YES / - / - / -
8125 / 81-Tl-203 / - / YES / YES / YES / - / YES
8128 / 81-Tl-204 / - / YES / YES / YES / - / YES
8131 / 81-Tl-205 / - / YES / YES / YES / - / YES
8225 / 82-Pb-204 / - / YES / YES / - / - / -
8228 / 82-Pb-205 / - / YES / YES / - / - / -
8237 / 82-Pb-208 / - / YES / YES / - / - / -
8325 / 83-Bi-209 / - / YES / YES / - / - / -
8434 / 84-Po-209 / - / YES / YES / YES / - / YES
9040 / 90-Th-232 / YES / YES / YES / YES / - / -
9134 / 91-Pa-232 / YES / YES / YES / YES / YES / -
9219 / 92-U-232 / YES / YES / YES / YES / YES / -
9222 / 92-U-233 / YES / - / YES / - / - / -
9225 / 92-U-234 / YES / - / YES / - / - / -
9237 / 92-U-238 / - / - / YES / - / - / -
9625 / 96-Cm-240 / YES / - / YES / - / - / -
9628 / 96-Cm-241 / YES / - / YES / - / - / -
9631 / 96-Cm-242 / YES / YES / YES / - / - / -
9634 / 96-Cm-243 / YES / YES / YES / - / - / -
9637 / 96-Cm-244 / YES / YES / YES / - / - / -
9640 / 96-Cm-245 / YES / YES / YES / - / - / -
9643 / 96-Cm-246 / YES / YES / YES / - / - / -
9646 / 96-Cm-247 / YES / YES / YES / - / - / -
9649 / 96-Cm-248 / YES / YES / YES / - / - / -
9652 / 96-Cm-249 / YES / - / YES / - / - / -
9655 / 96-Cm-250 / YES / - / YES / - / - / -
9864 / 98-Cf-253 / YES / - / YES / YES / YES / -

However, some problems when processing MF31,... MF40 files with NJOY-2012 have been identified. Table 8 shows a list of these materials.