F. Luo

Fast neutron scattering on Gallium target at 14.8 MeV

Abstract Benchmarking of evaluated nuclear data libraries was performed for ∼14.8 MeV neutrons on Gallium targets. The experiments were performed at China Institute of Atomic Energy (CIAE). Solid samples of natural Gallium (3.2 cm and 6.4 cm thick) were bombarded by ∼14.8 MeV neutrons and leakage neutron energy spectra were measured at 60° and 120°. The measured spectra are rather well reproduced by MCNP-4C simulations with the CENDL3.1, ENDF/B-VII and JENDL-4.0 evaluated nuclear data libraries, except for the inelastic contributions around E n = 10 – 13 MeV . All three libraries significantly underestimate the inelastic contributions. The inelastic contributions are further studied, using the Talys simulation code and the experimental spectra are reproduced reasonably well in the whole energy range by the Talys calculation, including the inelastic contributions.

Measurement of leakage neutron spectra from graphite cylinders irradiated with D-T neutrons for validation of evaluated nuclear data

A benchmark experiment for validation of graphite data evaluated from nuclear data libraries was conducted for 14MeV neutrons irradiated on graphite cylinder samples. The experiments were performed using the benchmark experimental facility at the China Institute of Atomic Energy (CIAE). The leakage neutron spectra from the surface of graphite (Φ13cm×20cm) at 60° and 120° and graphite (Φ13cm×2cm) at 60° were measured by the time-of-flight (TOF) method. The obtained results were compared with the measurements made by the Monte Carlo neutron transport code MCNP-4C with the ENDF/B-VII.1, CENDL-3.1 and JENDL-4.0 libraries. The results obtained from a 20cm-thick sample revealed that the calculation results with CENDL-3.1 and JENDL-4.0 libraries showed good agreements with the experiments conducted in the whole energy region. However, a large discrepancy of approximately 40% was observed below the 3MeV energy region with the ENDF/B-VII.1 library. For the 2cm-thick sample, the calculated results obtained from the abovementioned three libraries could not reproduce the experimental data in the energy range of 5-7MeV. The graphite data in CENDL-3.1 were verified for the first time and were proved to be reliable.

Measurements and analysis of leakage neutron spectra from multiple-slab sample assemblies comprising W,U,C, and CH 2 with D-T neutron irradiation

The accelerator driven subcritical system (ADS) is regarded as a safe and clean nuclear power system, which can be used for the transmutation of nuclear waste and the breeding of nuclear fuel. In this study, in order to validate nuclear data and the neutron transportation performance of the materials related to ADS, we measured the leakage neutron spectra from multiple-slab sample assemblies using 14.8 MeV D-T neutrons. Two types of assemblies comprising A-1 (W+U+C+CH2) and A-2 (U+C+CH2) were both built up gradually starting with the first wall. The measured spectra were compared with those calculated using the Monte Carlo code neutron transport coed (MCNP)-4C. A comparison of the results showed that the experimental leakage neutron spectra for both A-1 or A-2 were reproduced well by the three evaluated nuclear data libraries with discrepancies of less than 15% (A-1) and 12% (A-2), except when below 3 MeV. For 2-cm and 5-cm uranium samples, the CENDL-3.1 calculations exhibited large discrepancies in the energy range of 2-8 MeV and above 13 MeV. Thus, the CENDL-3.1 library for uranium should be reevaluated, especially around this energy range. It was significant that the leakage neuron spectra changed clearly when the latest material layer was added during the building of assemblies A-1 and A-2.