Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.

Abstract

This document provides the program plan for the out-ofreactor sodium heat transfer testing required to support the design, safety evaluation and initial reactor operation of FFTF driver-and test-fuel assemblies. These tests will employ electrically heated models of FFTF fuel assemblies and will be conducted under conditions of flow and heat generation simulating FTR operating conditions. The program will provide directly applicable laboratory information to support evaluation of: Clad temperatures and temperature gradients under normal and structurally distorted geometries Void initiation and propagation in loss of coolant accidents Emergency cooling operation and limits Postexpulsion cooling Operational limits for driver and test fuels.