Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 8 / 257 Term Explanation Conventional Island Criticality Decommissioning Decontamination Decontamination Factor Design Basis Earthquake Discharge Disposal Effluent Encapsulation Epoxy Resins Failure Fission Fuel Assembly Geological Disposal Facility Heterogeneous High Level Waste (HLW) The area of a nuclear facility site that contains the non-nuclear support buildings and services. A situation where a sufficient quantity of fissile material is assembled in the right geometry and concentration for a self sustaining nuclear chain reaction to take place. The administrative and technical actions taken to allow a nuclear site to be deconstructed and de-licensed after it has been shut down from a state of commercial operation. Removal of unwanted radioactive contamination by a chemical or mechanical process. The ratio of the quantity of contamination before clean up treatment to that after treatment. A measure of the efficiency of the clean up process. A postulated earthquake that a nuclear facility must be designed and built to withstand without loss to the systems, structures, and components necessary to assure public health and safety. The release of a waste into the environment without the intention of retrieval. The placing of waste in a predefined location for long-term storage without the intention to retrieve at a later date. Untreated waste-water or other liquid. The process of sealing radioactive materials to prevent leakage of contamination. Thermosetting epoxide polymer that cures when mixed with a catalyst. Where a system or operation does not complete its specified task or function. The splitting of a heavy nucleus of uranium or plutonium into at least two other nuclei and the release of a relatively large amount of energy. Two or three neutrons are usually released during this type of transformation. A matrix design module containing nuclear fuel that is designed to facilitate the loading and unloading of fuel from the reactor core. This is the planed radioactive waste disposal facility. It will be built deep underground and will offer shielding and long-term protection due to its geological features. A diverse mixture of components varying in size and nature. Waste for which account must be taken of the radioactive decay heat in its management. HLW requires shielding and cooling. Homogenisation The process by which a material is made uniform in composition and concentration. Interim Storage The storage of radioactive materials for an defined amount of time prior to final disposal.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 9 / 257 Term Intermediate Level Waste (ILW) Ion Exchange Resin K eff Leachability Legacy Lifecycle Low Level Waste (LLW) Neutron Flux Neutron Shield Nuclear Island Osmosis Passive Safety Periodically Polymer Pool Primary Circuit Explanation Waste for which the radioactivity content exceeds 4 GBq per tonne of alpha emitting radionuclides or 12 GBq per tonne of beta/gamma emitting radionuclides. An insoluble matrix substance, usually in the form of small individual beads, containing chemicals that is used to remove unwanted soluble radioactive materials from the EPR water auxiliary circuits. K eff (effective) represents the rate of growth of the nuclear fission reaction. It is the rate of change of the neutron population within a system i.e. the ratio of production to loss (leakage and absorption). A measure of the propensity and solubility of a species in water (predominantly ground water). Those wastes that have been long term (surface) stored pending a long-term disposal solution. It is the different stages within the existence of either the nuclear facility or the waste, ranging from creation through to either decommissioning or disposal. Waste that has radioactivity content less than the threshold for ILW. LLW forms that contain sufficient radioactive material to require action for the protection of people, but not so much that it requires shielding in handling or storage as Low Level Wastes are not heat generating. The number of neutrons passing through 1 square metre of area in 1 second. Materials with a high neutron capture cross section. The area of land on which the facilities that contain radioactive material are situated on a nuclear facility, typically containing the nuclear reactor core, steam generators and associated systems. It is shielded and separated from the outside world. Movement of a solvent (e.g. water) through a semi-permeable membrane from a solution of high solute concentration to one of low solute concentration through a concentration gradient. A form of safety precaution that does not require control systems or human intervention. After a certain point in time and at intervals thereto. For example annual reviews etc. A large (macro) molecule comprising of repeat units typically connected by covalent chemical bonds. An area that is filled with water that acts to absorb and moderate the radioactivity of radioactive material (such as spent fuel). This is the reactor coolant system. It involves the circulation of primary coolant stream moving from the reactor vessel, where heat is exchanged to the coolant, on to the steam generator where the heat is transferred to create steam, and back to the reactor vessel.
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