Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent

Modeling 3d Hydraulic Fracture Propagation and Thermal Fracturing Using Virtual Multidimensional Internal Bonds

Fracture propagation, especially for fractures emanating from inclined wellbores and closed natural fracture often involves Mode I, Mode II, and at times Mode III fracture pattern simultaneously. In this paper a Virtual Multidimensional Internal Bond (VMIB) model is presented to simulate 3D mixedmode fracture propagation. To represent the contact and friction between fracture surfaces, a threed...

Thermal Hydraulic Limits Analysis for the MIT Research Reactor Low Enrichment Uranium Core Conversion Using Statistical Propagation of Parametric Uncertainties

The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel element redesign from 15 to 18 plates per element, a reactor power upgraded from 6 MW to 7 MW is proposed in order to maintain the same reactor performance of the HEU core. Previous approaches in analyzing the impact of engineering uncerta...

Neutronic Evaluation of GCFR Core Diluents and Reflectors

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...

Turbulence Modeling Issues in Ads Thermal and Hydraulic Analyses

Accelerator Driven nuclear reactor Systems (ADS) have in several respects a prototypical character of the flow and cooling conditions combined with narrow operating conditions due to the materials engaged. E.g. the high local thermal load in the liquid metal cooled spallation target requires a very careful analysis by experimental and numerical means. Some of the main goals of the numerical ana...

Monte Carlo Neutronic Analysis of A Loosely Coupled Reactor*