Fissionable Elements - Substitute teacher looking for answer

  • Thread starter Thread starter bearspencer
  • Start date Start date
  • Tags Tags
    Elements Teacher
AI Thread Summary
The discussion centers on the distinction between fissionable and fissile elements, specifically addressing the minimum atomic mass (A) for fissionable elements, which is clarified to be around 232, exemplified by Th-232 and U-238. Participants note that elements like Gd and Dy, with atomic masses in the 153-156 range, are effective neutron absorbers but do not primarily undergo fission. The conversation also touches on the concept of spallation, where lighter elements can experience nucleon ejection from high-energy neutron interactions. There is a consensus that while heavier elements can release energy through fission, lighter elements typically do not undergo fission reactions, particularly those with atomic masses around 80. Overall, the discussion highlights the complexities of nuclear reactions and the need for accurate data to verify fission probabilities.
bearspencer
Messages
2
Reaction score
0
Got a question about fissionable (as opposed to fissile) elements.

I vaguely remember the minimum A number for (theoretically) fissionable elements is somewhere in the vicinity of 153 to 156.

But I don't recall the exact figure, neither google nor ask.com have been of help and I'd like to be able to go back to class this afternoon with the answer.

Anyone lend a hand?
 
Engineering news on Phys.org
It's more like 232, as in Th-232, which like U-238, is fissionable with fast neutrons. However Pa-231 apparently has a very small probability of spontaneous fission, but it itself is a decay/spallation product.

Ref: http://www.nndc.bnl.gov/chart/ - put cursor over element (Z,N), click on it, and then click Zoom 1.

A=153-156 is in the range of Gd (primarily 155, 157), Dy (161, 163) which are good neutron absorbers.

Lighter elements experience spallation in which a high energy neutron may knock out some nucleons ((n,p), (n,2n), (n,3n)), or an alpha particle.
 
Thanks for the reminder on spallation, and you're right, Gd and Dy have pretty decent cross sections.

But the thing is this; I distinctly remember being surprised that nuclei with a mass 80 amu or so below what I was used to seeing could fission and further surprised that the reaction was either endothermic or close to it.

Any thoughts as to how we could further check to verify the probabilities of induced fission with masses this low? I'd hate to think it was only my memory that was decaying.
 
One can search here for available reactions
http://www.nndc.bnl.gov/ensdf/

There do not appear any fission reactions with A=80.

http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/nucbin.html#c2
There is a comment that nuclides heavier than iron can release energy by fission, but I believe that in most cases, absorption of neutrons yields gamma emission, or other nucleons, or spallation - but not fission. Nature tends to take the easiest path to emit excess energy.
 
bearspencer said:
T
But the thing is this; I distinctly remember being surprised that nuclei with a mass 80 amu or so below
Are you thinking of the Iron minimum, in stars you can form heavier elements by fusion only upto Iron. After that it requires energy to join heavier elements and so presumably energy would be released if they split.
 
Hello everyone, I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information(power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.) for Material 2 is zero, while Material 1...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...

Similar threads

Replies
17
Views
4K
Replies
4
Views
3K
Replies
7
Views
3K
Replies
7
Views
4K
Replies
2
Views
2K
Back
Top