In this electronic article we use the one-dimensional multigroup neutron diffusion equation to reconstruct the neutron flux in a slab reactor from the nuclear parameters of the reactor, boundary and symmetry condition, initial flux and . The diffusion equation was solved analytically for one single homogeneous fuel region and for two regions considering fuel and reflector. To validate the metho...

The CITATION code based on neutron diffusion theory is used for flux calculation inside voluminous sample in prompt gamma activation analysis with an isotopic neutron source (241Am–Be). The code used the specific parameters related to energy spectrum source, irradiation system materials (shielding, reflector, etc.), geometry and elemental composition of the sample. The flux distribution (therma...

INTRODUCTION : The most informative neutron scattering investigations of the atomic-scale dynamical properties of crystalline solids nearly always require single crystal samples and – to date have mostly been carried out on crystal spectrometers at high-flux, reactor-based, steady-state neutron sources. Because such measurements tend to be made with small samples and are invariably flux-limited...

The neutron flux induced by radioactivity at the Gran Sasso underground laboratory is revisited. We have performed calculations and Monte Carlo simulations; the results offer an independent check to the available experimental data reported by different authors, which vary rather widely. This study gives detailed information on the expected spectrum and on the variability of the neutron flux due...

Axions may be produced thermally inside the cores of neutron stars (NSs), escape due to their feeble interactions with matter, and subsequently convert into X-rays in magnetic fields surrounding stars. We show that a recently-discovered excess hard X-ray emission 2 - 8 keV energy range from nearby Magnificent Seven isolated NSs could explained by this mechanism. These are unique they had previo...

MONNET is a fast-neutron source based on 3.5 MV tandem accelerator, located at the Geel (BE) site of Joint esearch Centre. It became operational in 2020. may deliver intense neutron beams energy range from 30 keV to 10.1 MeV and 12.8 24 MeV. Neutrons are generated by means nuclear reactions target material ( e.g. protons or deuterons lithium-7, tritium deuterium targets). delivers flux up 10 9 ...

The term ‘thermal flux’ implies a Maxwellian distribution of velocity and energy corresponding to the most probable velocity of 2200 m s−1 at 293.4 K. In order to measure the thermal neutron flux density, the foil activation method was used. Thermal neutron flux determination in paraffin phantom by counting the emitted rays of indium foils with two different detectors (Geiger– Muller counter an...