HETC and ANISN

For nuclear reaction data and nuclear reaction models, there are very wide engineering demands. Criticality calculation, shielding calculation, heat generation calculation, the evaluation of material damage, the evaluation of the radiation effect on human bodies and so on first come to mind. The circumstances in the neutron energy regions of lower than 15 MeV and higher than 15 MeV are outlined. In this report, the HETC based on intranuclear cascade-evaporation model and the ANISN which is the representative deterministic method are explained, and the results of using these calculation codes are compared. High energy transport code (HETC) is the extension of nucleon-meson transport Monte Carlo code so that it can be applied up to several hundreds GeV, and here, HETC-KFA-2 version incorporated in high energy radiation Monte Carlo elaborate system developed in Germany is discussed. As to the ANISN, the principle and the merit and demerit are described. The example of the calculation for the deep layer penetration of high energy neutrons by both methods is reported. (K.I.)