Prismatic VHTR neutronic benchmark problems

Application of Nodal Equivalence Parameters to Prismatic Vhtr Core Analysis

The generation of nodal cross sections and equivalence parameters for prismatic VHTR core components is discussed. For fuel-block cross section generation, a conventional single-block model with a reflective boundary condition is used. A one-dimensional fuel-reflector model is proposed for reflector cross section generation in order to accurately represent the significant neutron spectrum varia...

A new prismatic solid-shell element ’SHB6’ : assumed-strain formulation and evaluation on benchmark problems

Monte Carlo Simulation of Vhtr Particle Fuel with Chord Length Sampling

The Very High Temperature Gas-Cooled Reactor (VHTR) poses a problem for neutronic analysis due to the double heterogeneity posed by the particle fuel and either the fuel compacts in the case of the prismatic block reactor or the fuel pebbles in the case of the pebble bed reactor. Direct Monte Carlo simulation has been used in recent years to analyze these VHTR configurations but is computationa...

Neutronic Design of the Pb-ahtr

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...

Vhtr Numerical Benchmark Based on the Compact Nuclear Power Source Experiments

Twoand three-dimensional numerical benchmark cases based on the Compact Nuclear Power Source (CNPS) experiments conducted at the Los Alamos National Laboratory (LANL) in the 1980s have been specified for the validation and verification of Very High Temperature Reactor (VHTR) physics codes. Previous evaluation of the CNPS experiments has shown that the experimental tests could be useful for the ...