A novel simulation to calculate the neutronic parameters of TRIGA 2000 reactor using plate-type fuel has been performed. The plate used was produced by Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic based on INUKI’s dimension and current TRIGA’s configuration were simulated MCNPX. performed modeling complete reactor’s a fresh core state. We obtained kinetic parameter v...

The Low Energy Neutron Source (LENS) is based on Be(p,xn) reactions at proton energy up to 13 MeV. Its novel design employs a cylindrical light water reflector/moderator surrounding the Be target primary neutron source and a solid CH4 cold neutron moderator downstream from the Be target that is coupled to the reflector. The design of the Target/Moderator/Reflector (TMR) assembly was optimized w...

A nodal collocation method is proposed to compute the dominant Lambda modes of nuclear reactor core with a hexagonal geometry. This method is based on a triangular mesh and assumes that the neutronic flux can be approximated as a finite expansion in terms of Dubiner’s polynomials. The method transforms the initial differential eigenvalue problem into a generalized algebraic one, from which the ...

The cross sections of 235U were examined by WPEC Subgroup 18 focusing on the thermal and epithermal energy region. As a result, the ORNL group evaluated resolved resonance parameters of 235U up to 2.25 keV, which are currently used for all major libraries. Using the resolved resonance parameters, prediction accuracy of neutronic characteristics is satisfactory for thermal reactors. However, rec...

The 236U isotope is an important buildup product that is generated in the 235U fuel cycle and influences reactor neutronic calculations. The aim of the present work is to improve upon the existing neutron total cross section data for the strong 236U resonance at 5.467 eV. High accuracy neutron transmission measurements were performed using the time-of-flight technique at the Rensselaer Polytech...

This study (1) investigates the neutronic characteristics of the Pebble Bed Advanced High Temperature Reactor (PB-AHTR); (2) compares the PB-AHTR neutronic performance against those of the alternative design options of He-cooled high temperature reactors using either pebble (PBMR) or prismatic (VHTR) fuel and against a liquid-salt cooled design version of the latter (LS-VHTR); (3) studies the p...

The ARIES team has just completed the detailed design of ARIES-ACT-1 with aggressive physics and advanced SiC technology. Accurate neutronic characterizations of ARIES-ACT-1 are essential in determining its operational nuclear parameters. The neutron wall loading (NWL), tritium breeding ratio (TBR), and nuclear heating distribution are parameters that must be determined for tritium self-sustain...