clanENDF is an R package for reading nuclear data (here: cross sections for nuclear reactions) using the ENDF format (Evaluated Nuclear Data File). The package contains photonuclear data from IAEA for a few selected isotopes.
The ENDF format is described in detail in documents available at the Brookhaven National Laboratory website:
https://www.nndc.bnl.gov/endf/
For each ENDF file to be read by this package, one manually needs to identify the data of interest by means of the start and stop lines in the file. The file name and the line.start and line.stop are therefore the key parameters to the call to the main function:
read.endf()
The read.endf function can only read the pure data. It cannot read meta data from the endf file.
Meta data can, however, be assigned to the data. This facilitates data from different isotopes or processes etc.
The path to folder with the data is needed for you to read any endf-files. If you are reading the data provided with the package you can probably find the data using the second path defined below:
pn.full <- paste(getwd(),"/data/",sep="")
pn.full <- paste(.libPaths(),"/clanENDF","/data/",sep="")
The read.endf can then be called as follows;
df.H2.abs <- read.endf(
pn = pn.full,
fn = "g_1-H-2_0128.endf",
line.start = 91,
line.stop = 100,
Z = 1,
A = 2,
element = "H",
isotope = "H-2",
process = "total",
what = "cross section for (gamma,abs)")
The data read by the function should look like this:
# MeV barn file Z A element isotope process
#1 2.224 0.0000000 g_1-H-2_0128.endf 1 2 H H-2 total
#2 2.300 0.0006581 g_1-H-2_0128.endf 1 2 H H-2 total
#3 2.600 0.0011830 g_1-H-2_0128.endf 1 2 H H-2 total
#4 3.000 0.0018280 g_1-H-2_0128.endf 1 2 H H-2 total
#5 3.500 0.0022800 g_1-H-2_0128.endf 1 2 H H-2 total
#6 4.000 0.0024540 g_1-H-2_0128.endf 1 2 H H-2 total
#
# what
#1 cross section for (gamma,abs)
#2 cross section for (gamma,abs)
#3 cross section for (gamma,abs)
#4 cross section for (gamma,abs)
#5 cross section for (gamma,abs)
#6 cross section for (gamma,abs)
Note that the two first columns are the actual data from the ENDF file: (i) energy in MeV and (ii) cross section in barn (1 barn = 1e-24 cm2).
The data were extracted from line 91 to 100 in the g_1-H-2_0128.endf file (please note the annotations in the right side of the text below):
IAEA/PD-2019 H - 2 1 0 0
1.002000+3 1.996800+0 -1 0 38 1 128 1451
0.000000+0 0.000000+0 0 0 0 6 128 1451
0.000000+0 1.400000+8 0 0 0 2019 128 1451
0.000000+0 0.000000+0 0 0 76 4 128 1451
1- H - 2 NFD EVAL-AUG95 T.Murata 128 1451
NDS 163 109 (2020) DIST-JUN20 128 1451
----IAEA/PD-2019 MATERIAL 128 128 1451
-----PHOTO-NUCLEAR DATA 128 1451
------ENDF-6 FORMAT 128 1451
128 1451
History 128 1451
1995-08 Evaluation was performed by T.Murata (NFD) 128 1451
1995-08 Compiled by S. Chiba (JAERI) 128 1451
...
128 1451
MF=3 Photon Cross Sections 128 1451
MT=3 Total photo-absorption cross section 128 1451 MF3 data description
Incident energy below 10 MeV : 128 1451
Experimental cross sections/2/ were analyzed with a 128 1451
simplified Marshall & Guth model/3/. 128 1451
Incident energy above 10 MeV : 128 1451
Partovi/4/ gave theoretical cross section which reproduced 128 1451
experimental values fairly well. The theoretical results 128 1451
were basically fitted with the same model as described 128 1451
above. 128 1451
128 1451
MT=50 (g,n0) cross section 128 1451 MF50 data description
MT=50 (g,n0) cross section 128 1451
Same as the data of MT=3. 128 1451
128 1451
128 1451
References 128 1451
1) Murata, T. : JAERI-M 94-019, p.330 (1994). 128 1451
2) Allen, L.Jr.: Phys. Rev. 98, 705 (1955), 128 1451
Alexandrov, I.A.et al.: Soviet Phys. JETP 6, 472 (1958), 128 1451
Whalin, B.A. et al.: Phys. Rev. 101, 377 (1956), 128 1451
...
6) Dedrick, K.G.: Rev. Mod. Phys. 34, 429 (1962). 128 1451
128 1451
1 451 84 1 128 1451
3 3 13 0 128 1451
3 50 13 0 128 1451
6 50 65 0 128 1451
128 1 0
128 0 0
1.002000+3 1.996800+0 0 0 0 0 128 3 3
0.000000+0 0.000000+0 0 0 1 28 128 3 3
28 3 128 3 3
2.224000+6 0.000000+0 2.300000+6 6.581000-4 2.600000+6 1.183000-3 128 3 3 MF3 data line 91
3.000000+6 1.828000-3 3.500000+6 2.280000-3 4.000000+6 2.454000-3 128 3 3 MF3 data line 92
4.500000+6 2.474000-3 5.000000+6 2.416000-3 5.500000+6 2.318000-3 128 3 3 MF3 data line 93
6.000000+6 2.205000-3 8.000000+6 1.753000-3 1.000000+7 1.373000-3 128 3 3 MF3 data line 94
1.500000+7 8.528000-4 2.000000+7 5.882000-4 2.500000+7 4.350000-4 128 3 3 MF3 data line 95
3.000000+7 3.376000-4 3.500000+7 2.714000-4 4.000000+7 2.242000-4 128 3 3 MF3 data line 96
4.500000+7 1.893000-4 5.000000+7 1.629000-4 5.500000+7 1.425000-4 128 3 3 MF3 data line 97
6.000000+7 1.264000-4 7.000000+7 1.031000-4 8.000000+7 8.744000-5 128 3 3 MF3 data line 98
9.000000+7 7.622000-5 1.000000+8 6.764000-5 1.200000+8 5.483000-5 128 3 3 MF3 data line 99
1.400000+8 4.558000-5 128 3 3 MF3 data line 100
128 3 0
1.002000+3 1.996800+0 0 0 0 0 128 3 50
-2.224000+6-2.224000+6 0 0 1 28 128 3 50
28 3 128 3 50
2.224000+6 0.000000+0 2.300000+6 6.581000-4 2.600000+6 1.183000-3 128 3 50 MF50 data
3.000000+6 1.828000-3 3.500000+6 2.280000-3 4.000000+6 2.454000-3 128 3 50 MF50 data
4.500000+6 2.474000-3 5.000000+6 2.416000-3 5.500000+6 2.318000-3 128 3 50 MF50 data
6.000000+6 2.205000-3 8.000000+6 1.753000-3 1.000000+7 1.373000-3 128 3 50 MF50 data
...
I used this package (and the data it contains) to evaluate the ability of the Monte-Carlo software TOPAS to model photonuclear reactions. The results have been uploaded (March 2023) to the Topas user forum.
Data in ENDF-format can be found here:
https://www−nds.iaea.org/photonuclear/
https://www−nds.iaea.org/photonuclear/pdfilelist.html
The clanENDF package contain a small collection of cross section data from the IAEA photonuclear (2019) data base for a few isotopes:
H-2, O-12, Al-27, W-180, W-182, W-183, W-184, W-186.
You can find a plot of these data in the Github clanENDF folder:
IAEA-photonuclear-data-plot-001.pdf
The data file:
IAEA-photonuclear-2019.txt
contains data for all isotopes given above. This file is in the subfolder called data.
In most cases, I have first read the total cross section for the (gamma, any nuclear event)-reaction. This is the (gamma,abs) cross section as the gamma is absorbed.
Secondly, I have normally read the cross section for neutron production: (gamma, n) where n represents any number of neutrons produced by the event, regardless of any additional particles (protons, alphas etc.).
I have manually identified the relevant (hopefully correct) parts of the IAEA ENDF files and assigned meta data to them. Finally, I have joined everything into a single file.
From the plot in IAEA-photonuclear-data-plot-001.pdf, it is obvious that the neutron-production cross section for high energies are larger than (gamma,abs) at the same energy. I believe this is because the neutron production cross section is multiplied by the number of neutrons produced. In contrast, the "total" cross section given by (gamma,abs) only account for the absorbtion of the photon, and it does not matter how many neutrons (if any) are produced by the event.
You will need devtools to install the package. You will need clanTools, dplyr and lattice to run the package.
install.packages("devtools")
install.packages("dplyr")
install.packages("lattice")
library(devtools)
library(dplyr)
library(lattice)
install_github("claus-e-andersen/clanTools)
install_github("claus-e-andersen/clanENDF)
library(clanENDF)
library(clanTools)
To run the code using the data included with the package, please see the help for the demo function:
?IAEA.photonuclear.demo()
IAEA.photonuclear.demo()