Materials are evaluated for use as in-core diluents and as peripheral reflectors for Gas-Cooled Fast Reactor (GFR) service, using coupled Monte Carlo (MCNP) and isotopics (ORIGEN) codes. The principal performance indices compared were effects on beginning of irradiation multiplication factor, reactivity-lineated burnup, and coolant (here CO2) void reactivity. While low values of the macroscopic...

This paper describes the effect of cross-section data generated by several codes on calculated neutronic parameters. The Pressurized Water Reactor Mixed Oxide and Uranium (PWR MOX/UO2) Core Transient Benchmark case was chosen because it has been used widely to validate codes. in this study will be SRAC, Serpent, HELIOS NODAL3 code calculate parameters from each cross-section. are effective mult...

Due to the high confinement of closed fuel assemblies in Sodium-cooled Fast Reactors (SFR), liquid sodium filling space between these may vaporize case an important mechanical excitation (cavitation process). That phenomenon would therefore induce a specific force feedback leading neutronic response core. Neutronic SFR is indeed sensible deformation. Hence necessity have good prediction displac...

Time-dependent radiative transport is important in inertial confinement of fusion targets. The target must be illuminated with as symmetric a source as possible to ensure an isentropic compression. Once the fusion event begins, energy is taken away from the burn via radiation transport. This process represents a large percentage of the total energy loss. Similarly, neutron transport is importan...

This work reviews the historical literature associated with Dragon experiment and water boiler reactors operated at Los Alamos during Manhattan Project. Frisch’s invited talk given American Nuclear Society’s Fast Burst Reactor Conference held University of New Mexico in Albuquerque, Mexico, 1969 is quoted. From review, basic models for a boiler–type assembly (aqueous homogeneous reactor) were c...