Find specific reaction cross section in an ENDF file

In summary, an ENDF file is a type of nuclear data file that contains information about the cross sections, energies, and other properties of neutron-induced reactions. It can be opened with programs such as NJOY, ENDF-6 format reader, and ENDF-5 format reader. A specific reaction cross section is the probability of a particular nuclear reaction occurring when a neutron interacts with a nucleus, and can be found in an ENDF file by using a program or code to interpret the data. ENDF files can be used to calculate cross sections for experiments, but the accuracy may vary depending on the quality and completeness of the data and experimental conditions.
  • #1
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I'm trying to find specific reaction cross section 18O(p,n)18F
in proton + O-18 TENDL (ENDF format).

# p + 18O : (p,n) Total
# Q-value =-2.51902E+00
# E-threshold= 3.64964E+00
# # energies = 45
# E xs
1.000E+00 0.00000E+00
2.000E+00 0.00000E+00
3.000E+00 7.05780E+01
4.000E+00 1.83053E+02
5.000E+00 2.56205E+02
6.000E+00 2.81193E+02
7.000E+00 3.05196E+02
8.000E+00 3.10529E+02
9.000E+00 2.62915E+02
1.000E+01 1.82168E+02

It's provided in the link of 18O(p,n)
ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/xs/xs100000.tot
However, I can not find correspond value in ENDF file.
ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/lib/endf/O018-p.tendl
https://www.dropbox.com/s/07m9shznsx1jco6/9018.JPG


https://www.dropbox.com/s/07m9shznsx1jco6/9018.JPG
Please advise me.
 
Last edited:
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  • #2
Please let me rephrase my the question.
I'm looking for the cross section of 18O(p,n)18F in the ENDF file of TENDL provided in the link:
p + 18O : (p,n) ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/xs/xs100000.tot
18O(p,x)18F : Production of 18F ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/residual/rp009018.tot
Which are the same as expected.

However,the cross section of residual product 9.018000+3 the ENDF file is different as the links above
ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/lib/endf/O018-p.tendl
https://www.dropbox.com/s/07m9shznsx1jco6/9018.JPG

I'm very confused about the difference.
Please advise me.
Thanks in advance

Lee

  p+18O : (p,n) 9.018000+3 tendl ENDF
E(MeV) xs  
1 0.00000E+00 0.000000+0
2 0.00000E+00 0.000000+0
3 7.05780E+01 2.122838-1
4 1.83053E+02 3.758248-1
5 2.56205E+02 4.250742-1
6 2.81193E+02 4.218380-1
7 3.05196E+02 4.307818-1
8 3.10529E+02 4.175966-1
9 2.62915E+02 3.399558-1
10 1.82168E+02 2.289246-1
11 1.37536E+02 1.708513-1
12 1.03401E+02 1.282725-1
13 8.15315E+01 1.017085-1
14 6.03028E+01 7.595463-2
15 4.71970E+01 6.012981-2
16 3.71000E+01 4.783334-2
17 3.04388E+01 3.969633-2
18 2.42685E+01 3.202279-2
19 1.91105E+01 2.550941-2
20 1.57749E+01 2.130231-2
 
  • #3



Hi there,

I see that you are trying to find the specific reaction cross section for 18O(p,n)18F in proton + O-18 TENDL (ENDF format). I did some research and found that the cross section values for this reaction can be found in the following link: ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/xs/xs100000.tot. However, it seems that you are having trouble finding the corresponding value in the ENDF file: ftp://ftp.nrg.eu/pub/www/talys/tendl2013/proton_file/O/018/lib/endf/O018-p.tendl. I would suggest reaching out to the source of the ENDF file or the creators of TENDL for assistance in locating the specific value you are looking for. You can also try comparing the data in both files to see if you can find a match. I hope this helps and good luck with your search!
 

1. What is an ENDF file?

An ENDF file is a type of nuclear data file that contains information about the cross sections, energies, and other properties of neutron-induced reactions.

2. How do I open an ENDF file?

An ENDF file can be opened with a variety of programs, such as NJOY, ENDF-6 format reader, and ENDF-5 format reader. These programs are specifically designed for reading and manipulating ENDF files.

3. What is a specific reaction cross section?

A specific reaction cross section is the probability of a particular nuclear reaction occurring when a neutron interacts with a nucleus. It is typically measured in units of barns (b) and can vary depending on the energy of the neutron.

4. How do I find the specific reaction cross section in an ENDF file?

To find the specific reaction cross section in an ENDF file, you will need to use a program or code that can read and interpret the data in the file. This can be done by searching for the desired reaction and then extracting the corresponding cross section value.

5. Can I use an ENDF file to calculate cross sections for my own experiments?

Yes, ENDF files can be used to calculate cross sections for various nuclear reactions. However, it is important to note that the accuracy of these calculations may depend on the quality and completeness of the data in the ENDF file, as well as the specific conditions of your experiment.

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