Analyses of fusion integral benchmark experiments at JAEA/FNS with FENDL-2.1 and other recent nuclear data libraries

Neutron Flux Measurements in ITER-TBM Simulating Assemblies by means of Multi-Foil Activation Method

“…The cause of underestimation is not clarified yet. However, the tendency is similar to the past beryllium experiment 7) . Not only the thermal neutron peak but also the neutron flux around 4 eV is adjusted into downward, but the latter adjusting comes from the huge resonance peak of 4.9 eV in the 197 Au(n, ) 198 Au reaction and is not physical because no structure exists around 4 eV in the cross section data of beryllium.…”

“…In the past beryllium benchmark experiment 7) , it was pointed out that the calculation with FENDL-2.1 overestimated the neutron flux from 3 to 10 MeV, with which the present adjustment is consistent.…”

Integral Experiment on Beryllium with DD Neutrons for Nuclear Data Benchmarking

“…The reaction rates calculated for the 6 Li(n, )T and 235 U(n,fission) reactions show a very large overestimation; 30% for 6 Li and 60% for 235 U. This tendency is similar to that in the beryllium integral experiment 2) with DT neutrons previously carried out at FNS.…”

“…We chose beryllium as the first material for the integral experiment with DD neutrons because of its importance as a candidate material of a fusion reactor. Several problems of nuclear data evaluated for beryllium have been pointed out in the previous benchmark experiment 2) with DT neutrons. We expect that new information for verification of beryllium nuclear data would be acquired through the present integral experiment.…”

Measurement of tritium production rate distribution in natural LiAlO2/HDPE assembly irradiated by D-T neutrons

“…In order to assess the realistic margins for such self-sufficiency, the tritium breeding capability has to be calculated for the blanket concepts under development taking into account the uncertainties due to the nuclear data and codes used in the calculations [13]. Radiation transport tool MCNP and nuclear data library FENDL-2.1are adopted as a reference tool in fusion reactor nuclear analyzes [12,17]. FENDL-2.1 is a collection of the best evaluation for fusion applications from the world-wide nuclear data libraries such as ENDF/B-VI.8, JEFF-3.0, Brond-2.1 and JENDL-3.3 fusion file.…”