Dear all, I want to calculate the yield of Zr-89 produced by irradiating Y89 with 13 MeV proton. This is the input file. Y89.inp (3.5 KB), and this is the output file. Y89_53_sum.lis (1.9 KB) First, IRRPROFI is used to give the intensity. So,does ‘Total response is 1.64976 e-4’ in output file t…

Hi @wangxiaohe , Yes. Not only the intensity, but also the decay time, which you have selected as zero in your input. By the way, I do not see a RADDECAY card in your input although I am sure you had it, otherwise you would not have gotten any decay products. Just make sure it is there. Here I …

Dear Francisco. Thanks a lot for your response. 1，According to the results of IAEA, 88/39 will be produced, but the yield is seven orders of magnitude lower than 89/40. 2, The low-energy neutron cross section is very important for the calculation of the yield of Zr-89 (Y target) and Cu-64(Ni-64…

Hi, you are talking about (p,n) reactions, where low energy neutron cross sections, which refer to neutron induced reactions (n,*), have no relevance at all. The job here is done by the FLUKA interaction model for proton induced reactions, for which no library is needed. For an expected production…

Dear Francisco. Thanks a lot for your response again. 1， Yes, you are right. In the calculation of the yield of Cu-64(Ni-64 target), (p,n) reaction should be taken about. However, when I remove the LOW-MAT card and modify the MATERIAL card of NI-64 shown in the fig. The errors will be print out:…

Assuming that, as discussed, your goal is not sensitive to neutron reactions in Ni-64, you can input a LOW-MAT card to make use of the neutron cross sections of natural nickel in your NI-64 material slice, which are included in the FLUKA library . Note that the MATERIAL card defining COPPER is usele…

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