Integral test of International Reactor Dosimetry and Fusion File on graphite assembly with DT neutron at JAEA/FNS

Abstract

We perform an integral test of a new library of dosimetry cross section data, International Reactor Dosimetry and Fusion File release 1.0 (IRDFF 1.0), which has been released from the International Atomic Energy Agency recently. A pseudo-cylindrical graphite assembly is used with a DT neutron source at the fusion neutronics source facility of Japan Atomic Energy Agency. A lot of foils for measurements of dosimetry reaction rates are placed in the small space along the central axis in the assembly. After the DT neutron irradiation, forty dosimetry reaction rates are measured and are compared with calculated values, which are obtained by using a Monte Carlo neutron transport code MCNP5-1.40 and a nuclear data library ENDF/B-VII.1 with the IRDFF-v.1.03 as the response functions for the dosimetry reactions. The calculated results generally show good agreements with the experimental ones. The cross section data of the 68Zn(n,np)67Cu and 68Zn(n,d)67Cu reactions and the 113In(n,γ)114mIn reaction, which are not included in IRDFF-v1.03, are needed for the analysis of the 67Zn(n,p)67Cu reaction and the 115In(n,2n)114mIn reaction as the competitive reactions, respectively.