Abstract
In the measurement of neutron capture cross-sections of fissile isotopes, the fission channel is a source of background which can be removed efficiently using the so-called fission-tagging or fission-veto technique. For this purpose a new compact and fast fission chamber has been developed. The design criteria and technical description of the chamber are given within the context of a measurement of the 233U(n, γ) cross-section at the n_TOF facility at CERN, where it was coupled to the n_TOF Total Absorption Calorimeter. For this measurement the fission detector was optimized for time resolution, minimization of material in the neutron beam and for alpha-fission discrimination. The performance of the fission chamber and its application as a fission tagging detector are discussed.
Highlights
The neutron capture cross-sections of fissile isotopes are of interest in nuclear reactor as they influence the neutron economy of the reactor
In the measurement of neutron capture cross-sections of fissile isotopes, the fission channel is a source of background which can be removed efficiently using the so-called fission-tagging or fission-veto technique
The design criteria and technical description of the chamber are given within the context of a measurement of the 233U(n, γ) cross-section at the n_TOF facility at CERN, where it was coupled to the n_TOF Total Absorption Calorimeter
Summary
The neutron capture cross-sections of fissile isotopes are of interest in nuclear reactor as they influence the neutron economy of the reactor. This implies that in a measurement of the capture cross-section the γ-rays coming from the fission channel are a major source of background, which has to be taken care of in the analysis. In recent years new efforts have been made to measure the capture cross-sections of the fissile isotopes using the fission-tagging technique at different facilities [2,3,4,5]. With the goal of measuring the 233U(n, γ) cross-section a new fission detector was designed aiming at reducing the background from the detector and providing the necessary performance to reliably identify the fission γrays. The design of the described fission chamber (FICH) is adapted to the measurement of the 233U(n, γ) utilizing the fission chamber coupled to the n_TOF Total Absorption Calorimeter (TAC) [6] in experimental area 1 (EAR1) of the n_TOF facility [7]
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