Abstract
In the framework of studies concerning new fuel cycles and nuclear wastes incineration experimental data of the α ratio between capture and fission cross sections of 233U reactions play an important role in the Th/U cycle. The safety evaluation and the detailed performance assessment for the generation IV nuclear-energy system based on 232Th cycle strongly depend on this ratio. Since the current data are scarce and sometimes contradictory, new experimental studies are required. The measurement will take place at the neutron time-of-flight facility GELINA at Geel, designed to perform neutron cross section measurements with high incident neutron-energy resolution. A dedicated high efficiency fission ionization chamber (IC) as fission fragment detector and six C6D6 liquid scintilators sensitive to γ-rays and neutrons will be used. The method, based on the IC energy response study, allowing to distinguish between gammas originating from fission and capture, in the resonance region, will be presented.
Highlights
In the framework of studies concerning new fuel cycles and nuclear wastes incineration experimental data of the α ratio between capture and fission cross sections of 233U reactions play an important role in the Th/U cycle
The method, based on the ionization chamber (IC) energy response study, allowing to distinguish between gammas originating from fission and capture, in the resonance region, will be presented
Recent nuclear data sensitivity analysis [1, 2] of the breeding of the thorium cycle, have shown that the fissile regeneration is dominated by uncertainties in the α ratio between the capture and fission cross section of 233U
Summary
EPJ Web of Conferences study and design of innovative systems based on the use of 232Th cycle, accurate and consistent neutron cross section data are required. Recent nuclear data sensitivity analysis [1, 2] of the breeding of the thorium cycle, have shown that the fissile regeneration is dominated by uncertainties in the α ratio between the capture and fission cross section of 233U. New and accurate measurements for fission and neutron capture reactions of 233U are required to improve the reliability of cross section data. In this respect, the ACEN group of CENBG decided to focus its interest on these reactions. The experiments will be made at GELINA (Geel Linear Accelerator) neutron time-of-flight (TOF) facility at IRMM [9], a powerful pulsed white spectrum neutron source designed to perform neutron cross section measurements with high resolution for the incident neutron energy
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