Community Research and Development Information Service - CORDIS

FP7

Metallic fuels for advanced reactors

Funded under: FP7-EURATOM

Abstract

In the framework of the Generation IV Sodium Fast Reactor Program, the Advanced Fuel Project has conducted an evaluation of the available fuel systems supporting future sodium cooled fast reactors. This paper presents an evaluation of metallic alloy fuels. Early US fast reactor developers originally favored metal alloy fuel due to its high fissile density and compatibility with sodium. The goal of fast reactor fuel development programs is to develop and qualify a nuclear fuel system that performs all of the functions of a conventional fast spectrum nuclear fuel while destroying recycled actinides. This will provide a mechanism for closure of the nuclear fuel cycle. Metal fuels are candidates for this application, based on documented performance of metallic fast reactor fuels and the early results of tests currently being conducted in US and international transmutation fuel development programs.

Additional information

Authors: CARMACK W J, Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls (US);PORTER D L, Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls (US);HAYES S L, Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls (US);MEYER M K, Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls (US);BURKES D E, Nuclear Fuels and Materials Division, Idaho National Laboratory, Idaho Falls (US);CHANG Y I, Argonne National Laboratory, Argonne (US);LEE C B, Korea Atomic Energy Research Institute, Daejeon (KR);MIZUNO T, Japan Atomic Energy Agency, Narita-cho (JP);DELAGE F, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);SOMERS J, Institute of Transuranium Elements, Directorate General JRC, Karlsruhe (DE)
Bibliographic Reference: An oral paper given at: Second Symposium on Nuclear Fuels and Structural Materials for Next Generation Nuclear Reactors Held in: Anaheim, California (US)
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/doi:10.1016/j.jnucmat.2009.03.007
Record Number: 200910309 / Last updated on: 2009-09-22
Category: PUBLICATION
Original language: en
Available languages: en