Utilization of Hydride Materials in Nuclear Reactors

Yamawaki, Michio; Konashi, Kenji

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Paper Titles

Microstructural Control for Improving Properties of V-4Cr-4Ti Alloys, p.22
SiC/SiC Composites Irradiation Behaviour in Fusion Reactor Environment Conditions, p.27
Experimental Development at a Pilot Plant Scale of a Reduced Activation Ferritic/Martensitic RAFM Steel, Asturfer^®, p.36
Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor, p.41
Utilization of Hydride Materials in Nuclear Reactors, p.51
Progressive Development for Structural Integrity Quantification of Nuclear Grade Graphite in Very High Temperature Gas Cooled Reactor Core Environments, p.59
Multiscale Modelling of the Influence of Damage on the Thermal Properties of Ceramic Matrix Composites, p.65
General Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor, p.72
From High to Low Enriched Uranium Fuel in Research Reactors, p.78

Home > Advances in Science and Technology > 5th FORUM ON NEW MATERIALS PART B > Utilization of Hydride Materials in Nuclear...

Paper Title:

Utilization of Hydride Materials in Nuclear Reactors

Periodical	Advances in Science and Technology (Volume 73)
Main Theme	5th FORUM ON NEW MATERIALS PART B
Edited by	Pietro VINCENZINI, Hua-Tay LIN and Kevin FOX
Pages	51-58
DOI	10.4028/www.scientific.net/AST.73.51
Citation	Kenji Konashi et al., 2010, Advances in Science and Technology, 73, 51
Online since	October, 2010
Authors	Kenji Konashi, Michio Yamawaki
Keywords	Control Rod, Fast Reactor, Hydrides, Nuclear Waste
Price	US$ 28,-

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Abstract

Metal hydrides have high hydrogen atom density, which is equivalent to that of liquid water. Fast neutrons are efficiently moderated by hydrogen in metal hydrides. Metal hydrides have been studied for their potential application as nuclear materials in fast reactors (FRs). Two types of the utilizations of metal hydride in FRs are discussed in this paper. One is the utilization for transmutation target of long-lived nuclear wastes. Hydride fuel containing 237Np, 241Am and 243Am has been studied as a candidate transmutation target to reduce the radioactivity of long-lived nuclides included in reprocessed nuclear wastes. An application of the hafnium hydride has been investigated as neutron absorber in FRs. The core design has been performed to examine its characteristics and to evaluate the cost reduction effect. Demonstration of fabrication of hydride pin has been done with hydride pellets and stainless steel cladding. Coating technique of inner cladding surface has been also developed to reduce the permeation of hydrogen through stainless steel cladding. Physical and chemical properties of the pellet have been measured for designing the hydride pin. The integrity of the pellets at high temperature has been tested and their compatibility with sodium has also been tested. Irradiation test of hydrides has been performed in the fast experimental reactor, JOYO, at Japan Atomic Energy Association (JAEA).