Validation of Graphite Cross Section in Various Integral Experiments
Year: 2019
Type: conference-abstract
Abstract: This paper is focused on validation of graphite cross section. Graphite is an important material for a wide range of reactors such as HTR, RBMK or VHTR and MSR reactors belonging to the generation IV, which are now under development. However, there are still uncertainties in its cross sections. For purposes of mentioned validation, the set of measurements in the LR-0 core with graphite insertion and with graphite cube with external neutron source in its center was carried out. Other types of cores with larger graphite sensitivity are under investigation The cross-section validation by integral experiments is convenient option, because the physical quantities in integral experiments can usually be measured much more accurately than differential nuclear data. And this is also reason why the integral data are widely used for tuning of evaluated cross sections. Data obtained from measurement of neutron leakage spectrum with 252Cf in graphite cube center can be proposed for such kind of adjustments. The results in the LR-0 case are in satisfactory agreement with the calculations performed in MCNP6.1. In the case of leakage spectrum measurement from cube with side of d=30 cm some discrepancies occur. This might imply on incorrect angular treatment in graphite. Such disagreement does not have effect to critical calculations, but might play role in dosimetric calculations in graphite based reactors.
Language: English
Subfield: Nuclear Energy and Engineering
Field: Energy
Domain: Physical Sciences
Open Access status: diamond
OpenAlex ID: W2997366118