Fission Products that come from the MCNP output?

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Key fission products to consider from MCNP output include Iodine-135 and its decay to Xenon-135, which are crucial for reactor operation. Samarium-149 is another significant neutron poison, with Promethium-147 being less critical. For burnup calculations, Rhodium isotopes and Cesium isotopes are relevant, along with Neodymium isotopes. The importance of specific fission products varies significantly between thermal and fast reactor systems. Ultimately, the selection of important fission products should be tailored to the specific reactor type being modeled.
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What are the most important fission products?
What are the most important fission products should I include/care about that comes out from the MCNP output?
 
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This depends so much on what question you want to ask MCNP. X and 6 can calculate some forms of depletion but I don't know if they simulate poisoning and every fission product.

Iodine-135 and it's decay to Xenon-135 are especially relevant to reactor operation, but all fission products start as the double humped curve mess you see in textbooks.

https://en.wikipedia.org/wiki/Iodine_pit

If this doesn't help, tell us more about what the problem is.
 
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Certainly, Iodine-135 and it's decay to Xenon-135 are two important radionuclides. Samarium-149 (σ = 74,500 b) is another important poison, and to a lesser extent Promethium-147.
See - https://en.wikipedia.org/wiki/Neutron_poison#Transient_fission_product_poisons and following section.

For verifying burnup calculations, one would also look at Rh-103, -106; Cs-134/Cs-137; and Nd-143,145, and possibly Nd-146, -148.
 
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The answer is also going to depend strongly on what type of system you are modeling. The most important fission products for a thermal system are much different from the most important fission products in a fast system.

For example, Xe-135 is extremely critical in a thermal spectrum, but only modestly important in a fast spectrum.

In practice, the list of "important" fission products is usually tuned for each reactor type.
 
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Hello, I'm currently trying to compare theoretical results with an MCNP simulation. I'm using two discrete sets of data, intensity (probability) and linear attenuation coefficient, both functions of energy, to produce an attenuated energy spectrum after x-rays have passed through a thin layer of lead. I've been running through the calculations and I'm getting a higher average attenuated energy (~74 keV) than initial average energy (~33 keV). My guess is I'm doing something wrong somewhere...
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