Abstract
To validate nuclear data and code in the neutronics design of a hybrid reactor with thorium, integral experiments in two kinds of benchmark thorium assemblies with a D-T fusion neutron source have been performed. The one kind of 1D assemblies consists of polyethylene and depleted uranium shells. The other kind of 2D assemblies consists of three thorium oxide cylinders. The capture reaction rates, fission reaction rates, and (n, 2n) reaction rates in 232 Th in the assemblies are measured by ThO2 foils. The leakage neutron spectra from the ThO2 cylinders are measured by a liquid scintillation detector. The experimental uncertainties in all the results are analyzed. The measured results are compared to the calculated ones with MCNP code and ENDF/B-VII.0 library data.
Highlights
The fusion-fission hybrid energy reactor (FFHER) for energy production, consisting of a low-power magnetic confinement fusion device and a blanket with subcritical fuel region, is one of advanced reactors of applying fusion technologies to solve the present energy crisis [1]
The 232Th reaction rates are calculated by using MCNP code with ENDF/B-VII.0 library data
The spherical assemblies based on available depleted uranium (DU) and polyethylene shell (PE) shell, and the ThO2 cylinders are established
Summary
The fusion-fission hybrid energy reactor (FFHER) for energy production, consisting of a low-power magnetic confinement fusion device and a blanket with subcritical fuel region, is one of advanced reactors of applying fusion technologies to solve the present energy crisis [1]. Some conceptual blankets of FFHER based on the Th/U fuel cycle were designed [2]. The accuracy and reliability of evaluated nuclear data of thorium decide the validity of the physical design of the thorium-based blanket directly. A small number of integral neutronics experiments determining the 232Th reaction rates are available in the literatures, and for some cases large differences between calculations and experiments can be observed [3]. It is essential to perform the experiments for validating nuclear data and code [4]. The integral experiments on the thorium assemblies with a D-T neutron source have been performed in INPC [5,6,7,8,9]. The 232Th reaction rates in the assemblies and leakage neutron spectra are measured, separately. The measured results are compared to ones by using MCNP code with ENDF/BVII.0 library data
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