HTGR Knowledge Base
Conference Article: Determination Of A HTGR Radioactive Material Inventory
Christian Bourdeloie, CEA-Cadarache, Nuclear Technology Department, Saint-Paul-Lez-Durance Cedex, FRANCE; Pierre Marimbeau, CEA-Cadarache, Reactors Studies Department, Saint-Paul-Lez-Durance Cedex, FRANCEAbstract
High Temperature Gas-cooled Reactor systems have to deal with nuclear waste outputs with particular regard to graphite material as a major contribution in volume to HTGR waste fluxes. A HTGR was selected for the study based on activation calculations. Software packages required by neutronic calculations, developed by the CEA, make it possible to distinguish different locations inside the reactor with regard to neutron spectra. Assessments of amounts of radioactive materials were performed and provided a preliminary inventory of gaseous effluent releases, activities and nuclear waste fluxes issued from a HTGR in operation. Waste fluxes were subject to comparison with data concerning other nuclear power systems, such as PWRs. Results of these assessments provide information to support HTGR design studies, to issue specifications for materials, to help make technological choices and to contribute to defining reactor management strategies.
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key words: graphite; 14C; 3H; activation; radioactive inventory; nuclear waste; effluents
- Reference:
- Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
- International Atomic Energy Agency, Vienna (Austria)
- HTR-2004, pp:1-11
- International Atomic Energy Agency, Vienna (Austria)