Estimation of production cross-sections, transmutation and gas generation from radionuclides (A ∼50-60) in fusion environment

Appl Radiat Isot. 2022 Mar 2;184:110163. doi: 10.1016/j.apradiso.2022.110163. Online ahead of print.ABSTRACTDegradation of material properties under neutron irradiation generates a requirement for studying effects on materials in a fusion environment and optimizing radiation-resistant materials for future applications. In the present work, the durability of stainless steel (SS) alloy used in ITER-like fusion devices is studied. We have predicted the amount of radionuclides produced in the material upon neutron irradiation at various locations is determined using the ACTYS, neutron activation code, for a typical one-dimensional geometry of ITER-like fusion reactor. The ACTYS code is further used to determine the gas production from 55Fe, 59Ni, and other long-lived radionuclides in the material. To further stress the importance of gas production in fusion materials, a comparative study of gas production cross-sections as given in various standard data libraries is examined using TALYS-1.8 and is presented in the paper.PMID:35303629 | DOI:10.1016/j.apradiso.2022.110163
Source: Applied Radiation and Isotopes - Category: Radiology Authors: Source Type: research