- Nuclear installations in Germany
- Safety in nuclear energy
- Legal bases
- Licensing and supervision
- Safety philosophy
- Precautions and emergency response
- National committees
- International co-operation
- Reportable events
- Reporting procedure
- Incident registration centre
- International Nuclear Event Scale (INES)
- Reportable events in nuclear installations
- Reports on reportable events
- Shutdown and decommissioning
- Nuclear accidents
- What is nuclear waste management?
- Design approvals of transport packages
- Interim storage facilities
- What are interim storage facilities?
- Licensing of interim storage facilities for nuclear fuels
- Central interim storage facilities
- Decentralised interim storage facilities
- Interim storage facilities for radioactive waste with negligible heat generation
- Federal custody of nuclear fuels
- What is nuclear waste management?
- Foundation and development
- President of the BfE
- Laws and regulations
- Frequently applied legal provisions
- Handbook nuclear safety and radiation protection
- 1A Nuclear and radiation protection law
- 1B Other laws
- 1C Transport law
- 1D Bilateral agreements
- 1E Multilateral agreements
- 1F EU law
- 2 General administrative provisions
- 3 Announcements of the BMU and the formerly competent BMI
- 4 Relevant provisions and recommendations
- 5 Nuclear Safety Standards Commission (KTA)
- 6 Key committees
- Annex to the NS Handbook
- A 1 English translations of laws and regulations
- Dose coefficients to calculate radiation exposure
- Legal Basis
- BfE Topics in the Bundestag
Nuclear fuel supply and waste management
After having been used in the reactor, the fuel elements are spent and need to be disposed of. The procedural steps to treat, reprocess and dispose of the spent fuel elements are collectively referred to as nuclear fuel waste management.
Nuclear fuel supply stages
- Mining of uranium-containing ores
- Extraction of the uranium from the rock in milling facilities
The uranium content of the mined ores is typically 0.2 %. In a milling procedure the uranium is concentrated. The commercial product “Yellow Cake” is produced, which contains about 70 % to 75 % of uranium. The natural isotope composition of the uranium contained in the Yellow Cake is 0.7 % U-235 and 99.3% U-238
- Enrichment of the uranium isotope U-235 required for nuclear fission in light-water reactors
Nuclear power plants with light water reactors need uranium with a share of 3 % to 5 % of the fissile isotope U-235. Therefore the isotope U-235 needs to be concentrated (“enriched”) in the uranium. For this purpose, the uranium is converted into the chemical compound uranium hexafluoride (UF6) which can easily be transferred into the gas phase. Only in the gas phase is it easy to enrich the uranium. Enrichment methods use the slight difference in mass of the U-235 and U-238 molecules of the UF6 to separate these two components. The product of the enrichment plant is UF6 whose U-235 share is ca. 3 % to 5 %
- Fabrication of fuel elements
In a fuel element fabrication plant the uranium hexafluoride is converted into uranium dioxide (UO2). Tablets are pressed from UO2 powder that are sintered at temperatures above 1,700 °C, filled into cladding tubes made from zirconium alloys, and sealed gas-tight. This way single fuel rods are obtained that are assembled to fuel elements. Fuel elements of a pressurised water reactor contain about 500 kg uranium, those of a boiling-water reactor contain about 200 kg uranium.
In Germany, the following nuclear fuel supply plants are in operation:
Spent nuclear fuel management stages
Generally, fuel elements are used in reactors for three to four years. Due to the nuclear fissions, the share of the fissile U-235 decreases and radioactive fission products and significant amounts of plutonium generate, which is a new nuclear fuel. All activities to treat, reprocess and dispose of the spent fuel elements are collectively referred to as spent nuclear fuel management.
Two types of spent fuel element management are pursued:
- Reprocessing including recovery and reuse of the usable shares of plutonium and uranium:
The fuel elements are initially taken to an interim storage facility, where their activity decays. When they are reprocessed subsequently, reusable uranium and plutonium are separated from the radioactive fission products. Before they can be reused in a nuclear power plant, plutonium and uranium need to be reprocessed again to fuel elements. The radioactive fission products are solidified and then stored as radioactive waste.
- Direct disposal:
In direct disposal, the entire fuel element including the uranium and plutonium still contained therein is disposed of as radioactive waste after it has been stored intermediately in order for the short-lived radionuclides to decay and to reduce the heat generation that comes with the decay. For this purpose, the fuel elements are disassembled in a conditioning plant, placed into waste packages suitable for disposal and then disposed of as radioactive waste.
Since 2005, the law permits only the direct disposal of spent fuel elements in Germany.
- central and decentralised fuel element interim storage facilities and
- one (pilot) conditioning plant at Gorleben
are being operated as spent nuclear fuel management installations.
State of 2018.01.08