Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code

Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies

“…Design of assemblies with UO 2 fuel consists of 9 × 9 lattice configuration with 2 large water channels and 74 fuel rods of varying 235 U enrichment. Initial enrichment varies from Science and Technology of Nuclear Installations 3 3 wt% to 6.3 wt% for fuel mixtures (marked by numbers [1][2][3][4]. 16 fuel rods contain UO 2 -Gd 2 O 3 mixture (marked as G).…”

“…Void reactivity coefficient for BWR fuel has been studied for typical void fraction values of 0%, 40%, and 70% [2][3][4]. 0% and 70% void fractions were chosen in these studies, since they correspond to moderation conditions at the bottom and the top of the BWR fuel assembly during normal operation, respectively.…”

Neutronic analysis and validation of boiling water reactor core designed by MCNPX code

“…It is known that when the enrichment of the fuel increases the values of the thermal neutron flux decreases (Galahom et al, 2014). In spite of this, the thermal neutron flux values in the outer assemblies which fueled with lower enrichment have a lower thermal neutron flux as the surrounding assemblies fueled with higher enrichment.…”

Neutron and Gamma Spectrum Analysis of Kartini Research Reactor for Boron Neutron Capture Therapy (Bnct)

“…Several types of reactor have been designed and the criticality has been calculated using Monte Carlo N-Particle (MCNP) computer code [10][11][12]. MCNP also has been used for many calculation and simulation for BNCT purposes.…”

“…Thermal neutron fluxes recorded on the base of radial piercing beamport were 4.678×10 10 n/cm 2 s, with the epithermal neutron flux of 5.37×10 9 n/cm 2 s and fast neutron flux of 4.17×10 10 n/cm 2 s. The gamma flux on that side reaches 4.22×10 12 particles/cm 2 s. On the 92-cm-ranges from the base inside radial piercing beamport, both neutron and gamma flux decrease up to 5.11×10 8 n/cm2s for thermal neutron flux, 4.598×10 6 n/cm 2 s for epithermal neutron flux, 2.55×10 7 n/cm 2 s for fast neutron flux and 8.214×10 10 particles/cm 2 s for gamma flux. In conclusion, the spectrum yield from this study can be use to define the source spectrum of the simulations and optimations prior to BNCT pre-clinical trial (in vivo/in vitro test) use KRR radial piercing beamport.…”