Page 434 - Fundamentals of Magnetic Thermonuclear Reactor Design
P. 434

412     Fundamentals of Magnetic Thermonuclear Reactor Design


            of a neutron activation analysis. The dose rate of ionising radiation from tri-
            tium, DR , is assumed to be proportional to the concentration of tritium in air.
                    T
            Occupational exposure is calculated with consideration for the radiation effect
            weakening by local or temporary protective equipment, such as shields and her-
            metically sealed accoutrement.

            14.3.4  Radioactive Waste, Reactor Decommissioning

            Critical to the future of fusion energy and technology is the solution for the
            radioactive waste disposal problem. One of the advantages of the fusion reactor
            is that it produces a relatively small quantity of radioactive waste containing
            long-lived radioisotopes, while fission reactors mostly produce fission products.
            According to the PPCS-AB fusion reactor design estimates, the specific activity
            of long-lived radioisotopes is 45 TBq/(GW  · year), as compared to 4800 TBq/
                                              el
            (GW  · year) for a PWR-type fission reactor. At the same time, the design
                el
            experience with demonstration and commercial fusion reactors suggests that
            the mass of radioactive materials (RMs) removed from fusion reactors while
            in operation and after decommissioning per generated electric power will be
            much greater than for fission reactors. This makes the fusion radioactive waste
            disposal a serious challenge.
               Liquid and solid RMs are subdivided into very low-, low-, medium-, and
            high-activated materials (see Table A.14.1.4) [11]. They are collected and sorted
            with consideration for their radioactive, physical and chemical properties and
            subsequent handling methods. As part of the initial sorting procedure, they are
            divided into radioactive and non-radioactive waste and categorised according
            to their properties. Decontaminated low-activity dust-gaseous and liquid waste
            are dissolved to acceptable levels and discharged to air or water reservoirs. To
            reduce radioactivity, waste packages are kept prior to processing in temporary
            storage facilities for periods from a few days to a few tens of years. Condition-
            ing is undertaken as a safety measure to decrease waste volume and change it
            into a form that is suitable for transportation, storage and disposal [12].
               Liquid waste conditioning methods include sedimentation, extraction, ion
            exchange, distillation and solidification. Solid waste management techniques
            include compacting, burning and calcination (roasting at 500–700 K), while
            gaseous waste is treated by chemical absorption, adsorption and filtration. The
            conditioning end-products are immobilised solid RMs in the form of compact
            packages. When stored, they are separated by category and group. Long-term (a
            few tens of years) storage facilities include burial trenches, and above-ground
            and below-ground systems equipped with storage condition and radionuclide
            migration monitoring instruments. Deep underground repositories, salt forma-
            tions and caverns in stable geological formations are used where it is necessary
            to keep RM waste away for hundreds of years. Fusion reactors of the PPCS and
            ARIES type do not generate any RMs that would be classified as high-activated
            waste after 100 years disposal.
   429   430   431   432   433   434   435   436   437   438   439