2023/02/27
1. ActLib-J5ActLib-J5 is a set of activation cross section libraries for ORIGEN in SCALE6.2 and ORIGENS in SCALE6.0 produced from JENDL-5 and JENDL/AD-2017. ActLib-J5 used the JENDL-5
activation cross section data up to UPD11 in several JENDL-5 sub-libraries. The JENDL-5
activation cross section data include activation data of 794 nuclei, which are enough asactivation cross section libraries for ORIGEN and ORIGEN-S. On the contrary, JENDL/AD2017 includes activation data of only 311 nuclei, which are not enough. As described in Sec. 6,
the shortage of neuclei is no problem for ORIGEN-S three-group libraries because only data ofJENDL/AD-2017 are replaced in the bundled ORIGEN-S three-group library. However,insufficient nuclei were covered with JEFF/A-3.0 because the ORIGEN activation cross section
library is a stand alone. We will present the production methods and test results of these libraries
at the 30th International Conference on Nuclear Engineering (ICONE30) in May, 2023. Its
proceedings will be published in Mechanical Engineering Journal. Please refer MechanicalEngineering Journal with the references in Sec. 11 of this memorandum.
2. Directory structure of ActLib-J5
The directory structure of ActLib-J5 is as follows:ActLib-J5|- README_jp.txt : this file|- ORACT : activation cross section library set for ORIGEN in SCALE6.2|- ORACT-J5.200 : 200 group activation cross section library produced from JENDL5|- origen.rev03.j5a200g : 200-group activation cross section library file produced
from JENDL-5|- ORACT-J5.48 : 48-group activation cross section library produced from JENDL-5|- origen.rev03.j5a48g : 48-group activation cross section library file produced
from JENDL-5|- ORACT-JAD17.200 : 200-group activation cross section library produced fromJENDL/AD-2017|- origen.rev03.jad200g : 200-group activation cross section library file produced
from JENDL/AD-2017|- ORACT-JAD17.48 : 48-group activation cross section library produced fromJENDL/AD-2017|- origen.rev03.jad48g : 48-group activation cross section library file produced
from JENDL/AD-2017|- MAXS : activation cross section library set for ORIGEN-S in SCALE6.0|- MAXS-J5.zip : 199-group MAXS file set produced from JENDL-5 for three-groupactivation cross section libraries of ORIGEN-S in SCALE6.0 (compressed)|- origen.rev03.pwrj5.data : three-group activation cross section library ofORIGEN-S in SCALE6.0 produced from MAXS-J5 （ we used a similar
weighting function [attached flux file] as that used in the three-group activation
cross section library bundled in SCALE6.0 ORIGEN-S)|- MAXSJAD-2017.zip : 199-group MAXS file set produced from JENDL/AD-2017
for three-group activation cross section libraries of ORIGEN-S in SCALE6.0(update of MAXS/AD-2017）(compressed)|- origen.rev03.pwrad17.data : three-group activation cross section library of
ORIGEN-S in SCALE6.0 produced from MAXSJAD-2017（we used a similar
weighting function [attached flux file] as that used in the three-group activation
cross section library bundled in SCALE6.0 ORIGEN-S) [Combination ofneutron energy and neutron flux. Note that the neutron energy is not used.]|- origen-s.lib-prod.r1.f : a simple FORTRAN program which replaces parts of
ORIGEN-S three-group activation cross section library with MAXS files（updateof origen-s.lib-prod.f bundled in MAXS/AD-2017)|- array.inc : include file for origen-s.lib-prod.r1.f|- flux : a sample 199-group neutron spectrum to collapse 199-group MAXS files tothree-group data（similar as that used in the three-group activation cross section
library attached in SCALE6.0)|- maxs_to_3g.sh : a LINUX sample shell script which replaces parts of ORIGEN-S
three-group activation cross section library with MAXS files
3. Specifications of ORACT filel Processing code : AMPX-6 in SCALE6.2
l Temperature : 300 Kl Group structure : 200-group (the same as one of the libraries bundled in SCALE6.2) and48-group which was used in the JPDR (Japan Power Demonstration Reactor) activationanalysis (Sec. 11 specifies the energy boundary.)l Weighting function : Maxwell + 1/E + fission spectrum + 1/E above 10 MeV
l Infinite dilutionl Format : SCALE6.2 original binary format
4. Specifications of MAXS filel Processing code : PREPRO2018l Temperature : 300 K
l Group structure : 199-group (the same as VITAMIN-B6)
l Weighting function : Maxwell + 1/E + fission spectruml Infinite dilution

l Format : MAXS text format proposed by Dr. Okumura, JAEA. See Reference (5).
5. How to use ORACT files in COUPLE and ORIGEN(1) to copy an ORACT file which you use to the “data” directory in the SCALE6.2 directory.
(2) to rename the file name of unit number, assigned in the COUPLE code, in the“origen_filenames” file of the “data” directory in the SCALE6.2 directory with the namewithout “origen.rev03.” from the ORACT file name. For example, the name is “j5a200g”
for “origen.rev03.j5a200g”.
(3) to execute the COUPLE and ORIGEN codes. The ORACT file assigned is used in theCOUPLE and ORIGEN codes.
6. How to make a three-group cross section file from MAXS files
MAXS files have two kinds of files; 199 group cross section files (*.maxs-xs) and 199 groupisomer ratio files (*.maxs-isom). These files are not directly used in the ORIGEN-S code. The
following procedure is required.
(1) to collapse MAXS 199 group cross section data to three-group cross section data with anadequate neutron spectrum as the weighting function. It is desirable that the neutron
spectrum at a position where an ORIGEN-S calculation or similar one is adopted.
(2) to replace three-group cross section data of the ORIGEN-S activation cross section library(origen.rev03.pwrlib.data) with the corresponding three-group cross section data producedin (1).
A program “origen-s.lib-prod.r1.f” (update of “origen-s.lib-prod.f” in MAXS/AD-2017)attached in ActLib-J5 is used for the above procedure.
The LINUX shell script “maxs_to_3g.sh” attached in ActLib-J5 performs the above procedure
for all nuclei in a MAXS directory assigned in maxs_to_3g.sh. The following is how to use“maxs_to_3g.sh”.
(3) to compile origen-s.lib-prod.r1.f(4) to copy the three-group cross section file “origen.rev03.pwrlib.data” bundled in SCLAE6.0
to the “data” directory in the SCALE6.0 directory.
(5) to change MAX in line 4 of “maxs_to_3g.sh” to a full path directory where the MAXS filewhich you use exists.
(6) to replace the flux file with an adequate neutron spectrum.
(7) to execute “maxs_to_3g.sh”. The above (1) and (2) are performed and a new three-groupcross section file “origen.rev03.pwrmaxs.data” is produced. Note that data of nuclei andreactions which do not exist in the MAXS files in “origen.rev03.pwrmaxs.data” are thesame as those in origen.rev03.pwrlib.data.
7. How to use the new three-group cross section file in ORIGEN-S(1) to copy the new three-group cross section file to the “data/origen_data” directory in theSCALE6.0 directory.
(2) to rename “pwrlib” in line 7 of the “origen_filenames” file in the “data” directory of theSCALE6.0 directory with the name without “origen.rev03.” and “.data” from the newthree-group cross section file name. For example, the name is “pwrj5a” for“origen.rev03.pwrj5a.data”.
(3) to execute the ORIGEN-S code. ORIGEN-S uses the new three-group cross section file.
8. Download site of ActLib-J5
https://rpg.jaea.go.jp/main/en/ActLib-J5/
9. References of ActLIb-J5(1) Chikara Konno, Mami Kochiyama, Hirokazu Hayashi, “SCALE6.2 ORIGEN library
produced from JENDL/AD-2017,” JAEA-Conf 2021-001, pp. 132-137 (2022).
[https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2021-001.pdf](2) Chikara Konno, “Development of multi-group neutron activation cross-section library
fromJENDL/AD-2017,”
JAEA-Conf
2020-001,pp.
193-197(2020).
[https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2020-001.pdf](3) O. Iwamoto et.al, “Japanese evaluated nuclear data library version 5: JENDL-5,” J. Nucl.
Sci. Technol., 60, 1-60 (2023). [https://doi.org/10.1080/00223131.2022.2141903](4) K. Shibata, N. Iwamoto, S. Kunieda, F. Minato, O. Iwamoto, “Activation Cross-section
File for Decommissioning of LWRs,” JAEA-Conf 2016-004, pp.47-52 (2016).
[https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2016-004.pdf](5) K. Okumura, K. Kojima, K. Tanaka, “Development of multi-group neutron activation
cross-section library for decommissioning of nuclear facilities,” JAEA-Conf 2015-003,
pp.43-47 (2015). [https://jopss.jaea.go.jp/pdfdata/JAEA-Conf-2015-003.pdf](6) D.E. Cullen, “PREPRO 2019,” IAEA-NDS-0229 (2019).
10. Contact
konno.chikara@jaea.go.jp+81-29-282-5483
11. Appendix (48 group energy boundary)Group No.

Upper energy [eV]

Lower energy [eV]11.733e+07

1.492e+07

21.492e+07

1.419e+0731.419e+07

1.350e+0741.350e+07

1.000e+0751.000e+07

7.408e+0667.408e+06

6.065e+0676.065e+06

4.966e+0684.966e+06

4.066e+0694.066e+06

3.679e+06

103.679e+06

2.725e+06112.725e+06

2.365e+06122.365e+06

2.307e+06132.307e+06

2.231e+06

142.231e+06

1.653e+06

151.653e+06

1.353e+06

161.353e+06

8.629e+05178.629e+05

8.208e+05188.208e+05

7.427e+05197.427e+05

6.081e+05206.081e+05

4.979e+05

21

4.979e+05

3.688e+05223.688e+05

2.985e+05232.985e+05

2.972e+05

24

2.972e+05

1.832e+05

25

1.832e+05

1.111e+0526

1.111e+05

6.738e+0427

6.738e+04

4.087e+04

28

4.087e+04

2.479e+04292.479e+04

2.358e+0430

2.358e+04

1.503e+0431

1.503e+04

9.119e+03

32

9.119e+03

5.531e+0333

5.531e+03

3.355e+0334

3.355e+03

2.035e+0335

2.035e+03

1.234e+0336

1.234e+03

7.485e+02377.485e+02

4.540e+0238

4.540e+02

2.754e+02

39

2.754e+02

1.670e+0240

1.670e+02

1.013e+0241

1.013e+026.144e+01426.144e+01

3.727e+01433.727e+01

1.068e+01

44

1.068e+01

1.855e+0045

1.855e+00

4.140e-01

46

4.140e-01

5.452e-02

475.452e-02

3.341e-03

48

3.341e-03

3.310e-05