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Fusion Science and Technology
Latest News
Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
S.K. Sood, C. Fong, K.M. Kalyanam, O.K. Kveton, A. Busigin, D.M. Ruthven
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 299-304
Tritium Processing | doi.org/10.13182/FST92-A29761
Articles are hosted by Taylor and Francis Online.
Pressure Swing Adsorption (PSA), which is a well established industrial process for separating and purifying industrial gases, is proposed for recovery of hydrogen isotopes from the ITER (International Thermonuclear Experimental Reactor) solid breeder He purge stream. The PSA process has an inherent advantage over a recently proposed Temperature Swing Adsorption (TSA) design because it allows much faster cycling (10 vs. 480 min.) and therefore has significantly (48 times) lower tritium inventory. The maximum tritium inventory for a 10 minute PSA cycle is less than 0.5 g of tritium, thus meeting an important safety goal of ITER. The PSA process is based on using molecular sieve 5A at 77 K, with pressure cycling from 1 – 2 MPa during the adsorption cycle, to a rough vacuum during regeneration. Experiments have been carried out to confirm the H2/He adsorption isotherms on molecular sieve 5A, and to develop new data points at low H2 partial pressures and a temperature of 77 K. A dynamic simulation model has been developed to facilitate system design and optimization. Simulation results indicate that a single-pass hydrogen isotope recovery of 50–80% is achievable, and that hydrogen purity of more than 99% is possible to obtain from the blanket purge stream containing only 0.1% total hydrogen in helium. Further experiments are underway to verify the dynamic simulation results and to investigate alternative adsorbent materials.