Abstract
The gas-cooled fast reactor (GCFR) concept was investigated experimentally in the PROTEUS zero power facility at the Paul Scherrer Inst. during the 1970's. The experimental program was aimed at neutronics studies specific to the GCFR and at the validation of nuclear data in fast spectra. A significant part of the program used thorium oxide and thorium metal fuel either distributed quasi-homogeneously in the reference PuO{sub 2}/UO{sub 2} lattice or introduced in the form of radial and axial blanket zones. Experimental results obtained at the time are still of high relevance in view of the current consideration of the Gas-cooled Fast Reactor (GFR) as a Generation-IV nuclear system, as also of the renewed interest in the thorium cycle. In this context, some of the experiments have been modeled with modern Monte Carlo codes to better account for the complex PROTEUS whole-reactor geometry and to allow validating recent continuous neutron cross-section libraries. As a first step, the MCNPX model was used to test the JEFF-3.1, JEFF-3.1.1, ENDF/B-VII.0 and JENDL-3.3 libraries against spectral indices, notably involving fission and capture of {sup 232}Th and {sup 237}Np, measured in GFR-like lattices. (authors)
Highlights
The Gas-cooled Fast Reactor (GFR) concept has been proposed by Generation-IV (GEN-IV) initiative to develop safe, sustainable, reliable, proliferation-resistant and economic nuclear energy systems [1]
This papers focus on the spectral indices – including fission and capture in 232Th and 237Np - measured in the reference PuO2/UO2 lattices and their predictions with an MCNPX model specially developed for the PROTEUS-gas-cooled fast reactors (GCFRs) core
The new value for the 237Np fission cross section in J311 [7] is shown to underestimate the values obtained with all other libraries by about 4%, and the 237Np capture values obtained with B70 and B71 are 3 to 4% higher than for the other libraries
Summary
The Gas-cooled Fast Reactor (GFR) concept has been proposed by Generation-IV (GEN-IV) initiative to develop safe, sustainable, reliable, proliferation-resistant and economic nuclear energy systems [1]. In this context, the neutronic and thermal-hydraulic properties of the GFR have been recently analysed within the Nuclear Energy and Safety division of the Paul Scherrer Institute (PSI), using the in-house code system FAST [2]. The experimental programme comprised a large set of configurations to validate lattice and core calculation methods, and associated nuclear data libraries. Several core configurations were dedicated to nuclear data validation for the alternative 232Th/233U fuel cycle [3]
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