Appendix VII
Glossary111
ActinidesA series of chemical elements with atomic numbers from 89 to 109.
        Enriched uranium
    
    
        Uranium having a higher abundance of fissile isotopes than natural uranium.
        Enriched uranium is considered a special fissionable material.
    
        Enrichment plant (or isotope separation plant)
 An installation for
        the separation of isotopes of uranium to increase the abundance of U-235. The main
        isotope separation processes used in enrichment plants are gas centrifuge or gaseous
        diffusion processes operating with uranium hexafluoride (UF6) (which is also the
        feed material for aerodynamic and molecular laser processes). Other isotope separation
        processes include electromagnetic, chemical exchange, ion exchange, and atomic
        vapor laser and plasma processes.
    
        Fast reactor (fast neutron spectrum reactor) 
A reactor that, unlike
        thermal reactors, operates mainly with fast neutrons (neutrons in the energy range
        above 0.1 MeV) and does not need a moderator. Fast reactors are generally designed
        to use plutonium fuels and can be designed to burn actinides.
    
        Fissionable material
    
    
        In general, an isotope or a mixture of isotopes capable of nuclear fission.
        Isotopes U-233, U-235, Pu-239, and Pu-241 are referred to as both fissionable and fissile,
        while U-238 and Pu-240 are fissionable but not fissile.
    
        Fuel element (fuel assembly, fuel bundle) 
A grouping of fuel rods,
        pins, plates, or other fuel components held together by spacer grids and other structural
        components to form a complete fuel unit that is maintained intact during fuel transfer
        and irradiation operations in a reactor.
    
        Fuel fabrication plant
    
    
    
    
        An installation for manufacturing fuel elements.
    
        Geological repository
    
        Underground installation for the disposal of nuclear material, such as used
        fuel and/or high-level and transuranic nuclear waste.
    
        High enriched uranium (HEU)
   
   
        Uranium containing 19.8 percent or more of the isotope U-235.
    
        High-level radioactive waste (HLW)
    
        Highly radioactive materials produced as a byproduct of the reactions that
        occur inside nuclear reactors. HLW takes one of two forms: used reactor fuel when
        it is accepted for disposal; or second cycle aqueous rafinnate or other radioactive
        materials remaining after used fuel is reprocessed.
    
        Isotope
    
   
        One of two or more atoms of the same element that has the same number of
        protons in its nucleus but different numbers of neutrons. Isotopes have the same
        atomic number but different mass numbers.
    
        Lanthanides
   
    
        A series of chemical elements with atomic numbers from 57 to 71.
    
        Light water reactor (LWR)
    
    
        A power reactor that is both moderated and cooled by ordinary (light) water.
        LWR fuel assemblies usually consist of clad fuel rods containing uranium oxide pellets
        of low enrichment, generally less than 5 percent U235, or MOX having low plutonium
        content, generally less than 5 percent. There are two types of LWR: boiling water
        reactors (BWRs) and pressurized water reactors (PWRs).
    
        Low enriched uranium (LEU)
    
        Enriched uranium containing less than 19.8 percent of the isotope U-235.
    
        Mixed oxide (MOX)
    
   
        A mixture of the oxides of uranium and plutonium used as reactor fuel for
        the recycling of plutonium in thermal nuclear reactors (thermal recycling) and for
        fast reactors.
    
        Natural uranium
   
        Uranium as it occurs in nature, having an atomic weight of approximately
        238 and containing minute quantities of U-234, about 0.7 percent U-235, and 99.3 percent
        U-238. Natural uranium is usually supplied in raw form by uranium mines and concentration
        (ore processing) plants as uranium ore concentrate, most commonly the concentrated
        crude oxide U3O8, often called yellow cake.
    
        Nuclear fuel cycle
   
   
       The nuclear fuel cycle is a system of nuclear installations and activities
        interconnected by streams of nuclear material. The characteristics of the fuel cycle
        may vary widely from state to state, from a single reactor supplied from abroad
        with fuel to a fully developed system. Such a system may consist of uranium mines
        and concentration (ore processing) plants, thorium concentration plants, conversion
        plants, enrichment (isotope separation) plants, fuel fabrication plants, reactors,
        used fuel conventional reprocessing or more advanced chemical partitioning plants,
        and associated storage installations. The fuel cycle can be “open” by
        direct disposal of used nuclear fuel or “closed” in various ways: for
        example, by the recycling of enriched uranium and plutonium through thermal reactors
        (thermal recycle), by the reenrichment of the uranium recovered as a result of used
        fuel dissolution and partitioning, or by the burning of actinides in fast reactors.
    
        Plutonium
    
        A radioactive element that occurs only in trace amounts in nature, with
        atomic number 94 and symbol Pu.
    
        Reactor
    
        Any device in which a controlled, self-sustaining fission chain reaction can
        be maintained. Depending on their power level and purpose, reactors are subdivided
        into power reactors, research reactors, and critical assemblies.
    
        Reprocessing (conventional)—PUREX
    
   
        An installation for the chemical partition of nuclear material from fission
        products following dissolution of used fuel. The installation may also include the
        associated storage, head-end (cutting and dissolution) operations, conversion and
        analytical sections, a waste treatment facility, and liquid and solid waste storage.
        Conventional reprocessing involves the following steps: fuel receipt and storage;
        fuel decladding and dissolution; partition of uranium, plutonium, and possibly other
        actinides (for example, americium and neptunium) from fission products; partition
        of uranium from plutonium; and purification of uranium and plutonium. Once purified,
        uranium nitrate and plutonium nitrate may be converted, respectively, to UO2
        and PuO2 powder at an adjoining plant. Depending
        on the economics, these powders may be either indefinitely stored or recycled as
        MOX fuel into an LWR or advanced burner or breeder reactor. More advanced chemical
        partitioning involves separation of the actinides and some fission products that
        could simultaneously provide a fuel stream that is burnable in advanced reactors
        and is proliferation-resistant.
    
        Thorium
    
        A radioactive element with atomic number 90.
    
        Transmutation
    
    
        The conversion of one nuclide into another through one or more nuclear reactions,
        and more specifically, the conversion of an isotope of one element into an isotope
        of another element through one or more nuclear reactions.
    
        Transuranic elements
    
        Transuranic elements are the chemical elements with atomic numbers greater
        than 92.
    
        Uranium
    
        A naturally occurring radioactive element with atomic number 92.
    
        Used nuclear fuel
    
        Fuel from a reactor that is no longer efficient in power production because
        its fission process has slowed.
    
ENDNOTES
111. These definitions are taken primarily from the IAEA Safeguards Glossary, 2001 edition.