Finding Cross Section Data for Tungsten, Rhenium, Osmium & Iridium

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SUMMARY

This discussion focuses on the challenge of obtaining thermal neutron capture cross section data for tungsten, rhenium, osmium, and iridium isotopes, specifically for a project aimed at transmuting tungsten into platinum. Key isotopes of interest include Tungsten-186, Tungsten-187, Rhenium-187, Rhenium-188, Osmium-188, Osmium-189, Osmium-190, Iridium-191, and Iridium-192. The ENDF database does not contain osmium neutron cross section data, but alternative resources such as the JShimwell website provide access to various nuclear data evaluations, including EAF, JEFF, JENDL, and TALYS. Users are advised to conduct preliminary calculations on neutron flux requirements for feasible production rates.

PREREQUISITES
  • Understanding of thermal neutron capture cross sections
  • Familiarity with nuclear data evaluation formats such as ENDF, EAF, JEFF, JENDL, and TALYS
  • Basic knowledge of nuclear transmutation processes
  • Ability to perform back-of-the-envelope calculations for neutron flux
NEXT STEPS
  • Research thermal neutron capture cross sections for Tungsten-186 and Rhenium-187 using the ENDF database
  • Explore the JShimwell website for additional nuclear data evaluations
  • Investigate neutron flux calculations for practical production rates in nuclear transmutation
  • Review astrophysics papers on osmium neutron cross sections for potential insights
USEFUL FOR

This discussion is beneficial for nuclear physicists, researchers in nuclear engineering, and anyone involved in the study of nuclear transmutation and cross section data analysis.

zephramcochran
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Hi,

I'm doing a project to see the feasibility of transmuting tungsten into platinum on a small scale (maximum output of 1 kg per month). However, some of the cross section data that I need seems to be hard to find. Now because I am new to this, I don't know if its because no body has measured the data or because I simply am looking in the wrong place.

The data that I need are the thermal neutron capture cross sections for the following nuclides
(The radioactive ones have # signs):

Tungsten-186
Tungsten-187#
Rhenium-187#
Rhenium-188#
Osmium-188
Osmium-189
Osmium-190
Iridium-191
Iridium-192#

Can anyone point me in the right direction to get the data?
 
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ENDF Cross sections can be found on this site: http://www.nndc.bnl.gov/

It looks like the W-186->Re-187 and Re-187->Os-188 reactions are feasible with thermal cross sections in the hundreds of barns. However there is no neutron cross section data for Os in ENDF. Googling around I found a few astrophysics papers regarding Os neutron cross sections but I don't have memberships to download them.

Os-188 through Os-190 are stable so you would need several captures to get to Os-191 to make Ir-191. Then you need one more capture to get Pt-192.

Before you go further, you might want to do some back-of-the-envelope calculations to see what kind of neutron fluxes you will need to achieve macroscopic production rates. You need so many successive captures with only modest cross sections that it will not be possible to do this in an economically advantageous way. Neutrons are not free.
 
Last edited:
Hi there

Try this website for plotting and retrieving nuclear data http://jshimwell.com/ it is really easy to use

It has ENDF data (QuantumPion is correct ENDF does not currently contain Os data) like most other sites

The website also has other evaluations like EAF JEFF JENDL TALYS which do contain Os data. Experimental EXFOR data can also be added.

ShimPlotWell contains all the isotopes you have requested

The data can also be downloaded in text format.
 

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