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Production of database for heating number and damage cross section implemented in nuclear data process system FRENDY using the PHITS event generator

Iwamoto, Yosuke; Tada, Kenichi

Japan Atomic Energy Agency has developed the Japanese nuclear data processing system, FRENDY. For the calculation method of heating number and damage cross section under the neutron irradiation on materials, the energy balance method in the nuclear data processing system, NJOY, has been widely used. However, it can not calculate the heating number correctly for more than 200 nuclei. In this work, we calculated heating numbers and damage cross sections implemented in FRENDY for nuclear reactor materials with the neutron energy range between 10$$^{-11}$$ and 20 MeV using the PHITS event generator mode and the nuclear data library JENDL-4.0, and we compared them with results calculated by NJOY2012. As a result, damage cross sections calculated by PHITS generally agreed with results calculated by NJOY2012 for all nuclei. On the other hands, although NJOY2012 can not calculate heating numbers correctly for titanium, nickel and chromium, PHITS can calculate them correctly for all nuclei.

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