Materials Selection for the Canadian Supercritical Water-Cooled Nuclear Reactor Concept

Supercritical Water-cooled Nuclear Reactors: Review and Status

Modern concepts of nuclear reactors cooled with supercritical water are presented together with a short history. The supercritical water-cooled CANDU ((CANada Deuterium Uranium) is a registered trademark of AECL) reactor concept is fully discussed. Also, thermophysical properties at critical and supercritical pressures as well as heat transfer and hydraulic resistance at these conditions are pr...

A Materials Selection Protocol for Lightweight Actively Cooled Panels

This article provides a materials selection methodology applicable to lightweight actively cooled panels, particularly suitable for the most demanding aerospace applications. The key ingredient is the development of a code that can be used to establish the capabilities and deficiencies of existing panel designs and direct the development of advanced materials. The code is illustrated for a fuel...

Influence of Configuration on Materials Selection for Actively Cooled Combustors

The influence of combustor size and shape on material feasibility is explored using (structural and fuel) weight, as well as fuel economy as metrics. Amaterials selection methodology developed for actively cooled rectangular panels has been embellished to include cylindrical/annular configurations. The procedure incorporates an analytical model for temperature and stress distributions subject t...

A domain-specific analysis system for examining nuclear reactor simulation data for light-water and sodium-cooled fast reactors

Building a new generation of fission reactors in the United States presents many technical and regulatory challenges. One important challenge is the need to share and present results from new high-fidelity, high-performance simulations in an easily usable way. Since modern multiscale, multi-physics simulations can generate petabytes of data, they will require the development of new techniques a...

UWFDM-1256 A Lithium Self-Cooled Blanket Concept for the HAPL Conceptual Inertial Confinement Reactor